SEC Petition Evaluation Report

Petition SEC-00175, Addendum

Report Rev #: Addendum Report Submittal Date: March 12, 2015

Subject Expert(s): Christopher Miles, Mutty Sharfi

Site Expert(s): N/A

Petition Administrative Summary

Petition Under Evaluation

Petition # Petition 

Type

Petition

Receipt Date Qualification Date DOE/AWE Facility Name

SEC-00175 83.13 June 30, 2010 September 7, 2010 Grand Junction Facilities

Petitioner-Requested Class Definition 

All – Laborers, labor supervisors, painters, grounds personnel, and Fire Chief who worked at the Grand Junction 

Operations Office from 1943 through July 31, 2010.

Class Evaluated by NIOSH (In this Addendum)

The class of workers evaluated in this addendum includes all on-site personnel who worked at the Grand Junction

Facilities site from February 1, 1975 through July 31, 2010.

NIOSH-Proposed Class(es) to be Added to the SEC (In this Addendum)

All employees of the Department of Energy, its predecessor agencies, and its contractors and subcontractors who 

worked at the Grand Junction Facilities site in Grand Junction, Colorado, during the period from February 1, 1975 

through December 31, 1985, for a number of work days aggregating at least 250 work days, occurring either 

solely under this employment or in combination with work days within the parameters established for one or more 

other classes of employees in the Special Exposure Cohort.

Related Petition Summary Information 

SEC Petition Tracking #(s) Petition Type DOE/AWE Facility Name Petition Status

SEC-00175 83.13 Grand Junction One class added to the SEC

Related Evaluation Report Information 

Report Title DOE/AWE Facility Name

SEC Petition Evaluation Report for Petition SEC-00175 (dated January 12, 2011) Grand Junction Operations 

Office (now referred to as 

Grand Junction Facilities)

ORAU Lead Technical Evaluator: Christopher Miles ORAU Peer Review Completed By: Michael Kubiak

Peer Review Completed By: [Signature on File] 3/12/2015

Thomas Tomes Date

[Signature on File] 3/13/2015 SEC Petition Evaluation Reviewed By:

J. W. Neton Date

[Signature on File]` 3/13/2015 SEC Evaluation Approved By:

Stuart L. Hinnefeld Date
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

2 of 47

This page intentionally left blank
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

3 of 47

SEC-00175 Addendum Summary: Grand Junction Facilities

This evaluation report addendum by the National Institute for Occupational Safety and Health 

(NIOSH) addresses a class of employees proposed for addition to the Special Exposure Cohort (SEC)

per the Energy Employees Occupational Illness Compensation Program Act of 2000, as amended, 42 

U.S.C. § 7384 et seq. (EEOICPA) and 42 C.F.R. pt. 83, Procedures for Designating Classes of 

Employees as Members of the Special Exposure Cohort under the Energy Employees Occupational 

Illness Compensation Program Act of 2000.

NIOSH presented an SEC-00175 Special Exposure Cohort Evaluation Report (NIOSH, 2011) 

regarding the Grand Junction Facilities (Grand Junction – previously designated as the Grand Junction 

Operations Office [GJOO]) to the Advisory Board on Radiation and Worker Health (Advisory Board) 

on February 24, 2011. In its report, NIOSH evaluated the feasibility of reconstructing radiation doses 

for all workers who worked at Grand Junction during the time period of 1943 through July 31, 2010. 

Based on its research at that time, NIOSH defined a single class of employees for which it could not 

estimate radiation doses with sufficient accuracy from March 23, 1943 through January 31, 1975. 

The internal dose reconstruction infeasibility identified by NIOSH for the March 23, 1943 through 

January 31, 1975 time period was due to a lack of data necessary to fully reconstruct internal doses 

during that time period, including doses from radon. By February 1, 1975, sampling operations had 

ended, and the large quantities of uranium concentrate, the source of radon emissions, had been 

removed from the site. The external dose reconstruction infeasibility identified by NIOSH for the 

March 23, 1943 through December 31, 1959 time period was due to a lack of external dose 

monitoring data. Beginning in 1960, worker exposures were reported to the Atomic Energy 

Commission (AEC) and DOE in the form of annual reports. Those reports provide sufficient 

information to bound external exposures at Grand Junction after 1959.

NIOSH concluded in its initial SEC-00175 Evaluation Report that internal dose reconstruction was

likely feasible for the period from February 1, 1975 through July 31, 2010, and that external dose 

reconstruction was likely feasible for the period from January 1, 1960 through July 31, 2010. NIOSH 

also found it likely feasible to reconstruct occupational medical dose for the Grand Junction workers 

with sufficient accuracy from March 23, 1943 through July 31, 2010.

During its presentation of the initial SEC-00175 Evaluation Report to the Advisory Board, NIOSH 

indicated that it had recently received additional data that was pertinent to the post-1975 period at 

Grand Junction, which had not yet been fully evaluated. At that time, NIOSH indicated that it would 

continue its evaluation of the post-1975 period and include its findings in a revision to the SEC-00175 

Evaluation Report, or in the issuance of an addendum. The purpose of this addendum is to fulfill that 

commitment.

NOTE: This SEC-00175 Evaluation Report Addendum only addresses those sections in the NIOSH 

2011 Grand Junction Operations Office (GJOO) (now referred to as Grand Junction Facilities) 

Site Evaluation Report that require further discussion; therefore, the section numbering and table 

numbering is not contiguous. For context, some of the original surrounding text may be included 

with the revised text. The sections requiring additional discussion begin below.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

4 of 47

Petition Evaluation Report Addendum Summary

Class Evaluated by NIOSH (in this Addendum)

In its 2011 Evaluation Report, NIOSH defined a single class of employees for which it could not 

estimate radiation doses with sufficient accuracy from March 23, 1943 through January 31, 1975. 

NIOSH also concluded in the 2011 evaluation that internal and external dose reconstruction were 

likely feasible for the period February 1, 1975 through January 31, 2010. Since issuing the 2011 

SEC-00175 Evaluation Report, NIOSH has continued its evaluation of the post-1975 period. This 

current report documents that effort. The class of workers evaluated in this SEC-00175 Addendum 

includes all on-site personnel who worked at the Grand Junction Facilities site from February 1, 1975 

through July 31, 2010.

NIOSH-Proposed Class to be Added to the SEC

Based on its continued research, and consideration of uranium and thorium operations discovered after 

the issuance of its 2011 Evaluation Report, NIOSH has concluded that there are insufficient data 

available to estimate uranium or thorium intakes, including their associated progeny, prior to 1986. 

NIOSH has therefore expanded the class of employees for which NIOSH recommends inclusion in the 

SEC. The NIOSH-proposed class resulting from this present evaluation includes all employees of the 

Department of Energy, its predecessor agencies, and its contractors and subcontractors who worked at 

the Grand Junction Facilities site in Grand Junction, Colorado, during the period from February 1, 

1975 through December 31, 1985, for a number of work days aggregating at least 250 work days, 

occurring either solely under this employment or in combination with work days within the 

parameters established for one or more other classes of employees in the Special Exposure Cohort.

Feasibility of Dose Reconstruction

In addition to the dose reconstruction infeasibilities identified in the 2011 Evaluation Report, NIOSH 

now finds it is not feasible to estimate internal exposures with sufficient accuracy for all workers at 

the site from February 1, 1975 through December 31, 1985. In this SEC-00175 Addendum, NIOSH

has determined that there is insufficient information to estimate internal dose from intakes of uranium, 

thorium, and their associated progeny, from February 1, 1975 through December 31, 1985. NIOSH 

has determined however, that partial internal dose reconstructions can be performed for workers who 

were monitored for uranium or thorium intakes during this period.

With the exception of the class defined for the period from February 1, 1975 through December 31, 

1985, per EEOICPA and 42 C.F.R. § 83.13(c)(1), NIOSH has established that it has access to 

sufficient information to: (1) estimate the maximum radiation dose, for every type of cancer for which 

radiation doses are reconstructed, that could have been incurred in plausible circumstances; or (2) 

estimate radiation doses more precisely than an estimate of maximum dose. Information available to 

NIOSH is sufficient to document or estimate the maximum internal and external potential exposure to 

members of the evaluated class under plausible circumstances during the specified period from 

January 1, 1986 through July 31, 2010.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

5 of 47

The NIOSH dose reconstruction feasibility findings for this current evaluation are based on the 

following:

• Principal sources of internal radiation dose for members of the evaluated class included exposures 

to natural uranium and thorium and their decay products. The modes of exposure were inhalation 

and ingestion during the processing of ores or ore concentrates or during the subsequent resuspension of these materials.

• In this current evaluation, NIOSH has determined that there are insufficient data available to 

bound intakes of uranium, thorium, and their associated long-lived progeny, for the period from 

February 1, 1975 through December 31, 1985. Although sampling operations had ended by 

February 1, 1975, and the large quantities of uranium concentrate (the major source of radon 

emissions) had been removed from the site, NIOSH has determined that smaller-scale operations 

involving crushing and grinding of uranium and thorium ores continued at least through 1988. 

Operations in the Sample Plant involving high-grade uranium and thorium ores, particularly the 

crushing and grinding operations, were a potential source of internal exposures. NIOSH has now 

concluded that there are insufficient internal dosimetry data or air monitoring data available to 

estimate uranium or thorium intakes prior to 1986. Beginning in the first quarter of 1986, air 

monitoring data are available which are sufficient to bound intakes of uranium and thorium until 

the site internal dosimetry program was fully implemented by 1991.

• Based on the lack of internal dose monitoring data or air monitoring data for Grand Junction 

Facilities workers during the period from February 1, 1975 through December 31, 1985, NIOSH 

has determined that sufficiently accurate internal dose reconstruction is not feasible. However, 

NIOSH has identified sufficient information and data to support bounding internal dose estimates

for the period from January 1, 1986 through July 31, 2010, using available air monitoring and 

bioassay data.

• NIOSH finds that it is likely feasible to reconstruct dose from radon for the Grand Junction 

Facilities workers with sufficient accuracy from February 1, 1975 through July 31, 2010.

• NIOSH finds that it is likely feasible to reconstruct occupational medical dose for the Grand 

Junction Facilities workers with sufficient accuracy from February 1, 1975 through July 31, 2010.

• NIOSH finds that it is likely feasible to reconstruct external dose for the Grand Junction Facilities 

workers with sufficient accuracy from February 1, 1975 through July 31, 2010.

Pursuant to 42 C.F.R. § 83.13(c)(1), NIOSH determined that there is insufficient information for the 

period from February 1, 1975 through December 31, 1985 to either: (1) estimate the maximum 

radiation dose, for every type of cancer for which radiation doses are reconstructed, that could have 

been incurred under plausible circumstances by any member of the class; or (2) estimate the radiation 

doses of members of the class more precisely than a maximum dose estimate.

Although NIOSH found that it is not possible to completely reconstruct radiation doses for the 

proposed class, NIOSH intends to use any internal and external monitoring data that may become 

available for an individual claim (and that can be interpreted using existing NIOSH dose 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

6 of 47

reconstruction processes or procedures). Therefore, dose reconstructions for individuals employed at 

the Grand Junction Facilities during the period from February 1, 1975 through December 31, 1985, 

but who do not qualify for inclusion in the SEC, may be performed using these data as appropriate.

NIOSH concludes pursuant to 42 C.F.R. § 83.13(c)(1), that there is sufficient information to either: 

(1) estimate the maximum radiation dose, for every type of cancer for which radiation doses are 

reconstructed, that could have been incurred under plausible circumstances by any member of the 

class; or (2) estimate the radiation doses of members of the class more precisely than a maximum dose 

estimate for the period at Grand Junction Facilities from January 1, 1986 through July 31, 2010.

Health Endangerment Determination

Per EEOICPA and 42 C.F.R. § 83.13(c)(3), a health endangerment determination is required because 

NIOSH has determined that it does not have sufficient information to estimate dose for the members 

of the proposed class from February 1, 1975 through December 31, 1985.

NIOSH did not identify any evidence supplied by the petitioners or from other resources that would 

establish that the proposed class was exposed to radiation during a discrete incident likely to have 

involved exceptionally high-level exposures. However, evidence indicates that some workers in the 

proposed class may have accumulated substantial chronic exposures through episodic intakes of 

radionuclides, combined with external exposures to gamma, beta, and neutron radiation. 

Consequently, NIOSH has determined that health was endangered for those workers covered by this 

evaluation who were employed for at least 250 aggregated work days either solely under their 

employment at Grand Junction Facilities or in combination with work days within the parameters 

established for other SEC classes. For the period from January 1, 1986 through July 31, 2010, a 

health endangerment determination is not required because NIOSH has determined that it has 

sufficient information to estimate dose for the members of the evaluated class.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

7 of 47 

Table of Contents

Petition Evaluation Report Addendum Summary ................................................................................... 4

1.0 Purpose and Scope .......................................................................................................................... 9

3.2 Class Evaluated by NIOSH ................................................................................................... 9

3.3 NIOSH-Proposed Class to be Added to the SEC .................................................................. 9

4.3 Facility Employees and Experts .......................................................................................... 10

4.5 NIOSH Site Research Database .......................................................................................... 11

5.0 Radiological Operations Relevant to the Class Evaluated by NIOSH ......................................... 11

5.1.1 Grand Junction General Operations ........................................................................ 11

5.2.1 Internal Radiological Exposure Sources from Grand Junction Operations ............. 13

5.2.1.1 Uranium .................................................................................................... 13

5.2.1.2 Thorium .................................................................................................... 14

6.1 Available Grand Junction Internal Monitoring Data ........................................................... 14

6.2 Available Grand Junction Operations External Monitoring Data ....................................... 25

7.2 Evaluation of Bounding Internal Radiation Doses at Grand Junction ................................ 26

7.2.1 Evaluation of Bounding Process-Related Internal Doses ........................................ 26

7.2.1.1 Urinalysis Information and Available Data .............................................. 26

7.2.1.2 Fecal Samples ........................................................................................... 27

7.2.1.3 Airborne Levels ........................................................................................ 27

7.2.3 Methods for Bounding Internal Dose at Grand Junction ......................................... 27

7.2.3.1 Methods for Bounding Operational Period Internal Dose ........................ 27

7.2.4 Internal Dose Reconstruction Feasibility Conclusion ............................................. 32

7.5 Summary of Feasibility Findings for Petition SEC-00175, Addendum .............................. 32

8.0 Evaluation of Health Endangerment for Petition SEC-00175 ...................................................... 33

9.0 Class Conclusion for Petition SEC-00175 ................................................................................... 34

10.0 References for this Addendum ..................................................................................................... 35

Attachment 2: Data Capture Synopsis ................................................................................................... 41

Tables 

Table 6-1: Grand Junction Office Bioassay Data in the Site Research Database ................................. 15

Table 6-2: Grand Junction Office Air Monitoring Data in the Site Research Database ....................... 22

Table 6-7: External Dosimetry Files ..................................................................................................... 25

Table 7-3a: Summary of Addendum Feasibility Findings for SEC-00175 ........................................... 33
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

8 of 47

This page intentionally left blank
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

9 of 47

SEC Petition Evaluation Report Addendum for SEC-00175

1.0 Purpose and Scope

This report evaluates the feasibility of reconstructing doses for all on-site personnel who worked at 

Grand Junction Facilities from February 1, 1975 through July 31, 2010. It provides information and 

analyses germane to considering a petition for adding a class of employees to the congressionallycreated SEC. 

This report does not make any determinations concerning the feasibility of dose reconstruction that 

necessarily apply to any individual energy employee who might require a dose reconstruction from 

NIOSH. This report also does not contain the final determination as to whether the proposed class 

will be added to the SEC.

This evaluation was conducted in accordance with the requirements of EEOICPA, 42 C.F.R. pt. 83,

and the guidance contained in the Division of Compensation Analysis and Support’s (DCAS) Internal 

Procedures for the Evaluation of Special Exposure Cohort Petitions, OCAS-PR-004.1

3.2 Class Evaluated by NIOSH

NIOSH concluded in its 2011 SEC-00175 Evaluation Report that internal and external dose 

reconstruction was likely feasible for the period from February 1, 1975 through July 31, 2010. 

NIOSH also concluded in that 2011 evaluation that it is likely feasible to reconstruct occupational 

medical dose for the Grand Junction workers with sufficient accuracy. During its February 2011 

presentation of the initial SEC-00175 Evaluation Report to the Advisory Board, NIOSH indicated that 

it had recently received additional data that were pertinent to the post-1975 period at Grand Junction 

which had not yet been fully evaluated. At that time, NIOSH indicated that it would continue its 

evaluation of the post-1975 period. The class of workers evaluated in this addendum includes all onsite personnel who worked at the Grand Junction Facilities site from February 1, 1975 through July 

31, 2010.

3.3 NIOSH-Proposed Class to be Added to the SEC

Based on its research of the class under evaluation, NIOSH has defined a single class of employees for 

which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSH-proposed class 

to be added to the SEC includes all employees of the Department of Energy, its predecessor agencies, 

and its contractors and subcontractors who worked at the Grand Junction Facilities site, in Grand 

Junction Colorado, during the period from February 1, 1975 through December 31, 1985, for a 

number of work days aggregating at least 250 work days, occurring either solely under this 

employment or in combination with work days within the parameters established for one or more 

other classes of employees in the SEC.

 1 DCAS was formerly known as the Office of Compensation Analysis and Support (OCAS).
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

10 of 47

4.3 Facility Employees and Experts

To obtain additional information for its initial evaluation of Petition SEC-00175, NIOSH interviewed 

eight former Grand Junction employees and one former Grand Junction contractor. Those interviews

were conducted by telephone by members of the ORAU Team; the references for those documented 

communications are identified in Section 4.3 of the initial SEC-00175 Evaluation Report. As part of 

this current evaluation, NIOSH conducted eight additional interviews of former Grand Junction 

Facility employees. References for these more recent interviews are provided below:

• Personal Communication, 2014a, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; October 15, 2014; SRDB Ref ID: 137017

• Personal Communication, 2014b, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; October 17, 2014, 12:00 PM EST; SRDB Ref 

ID: 137895

• Personal Communication, 2014c, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; October 21, 2014, 3:00 PM EST; SRDB Ref ID: 

137019

• Personal Communication, 2014d, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; October 31, 2014; SRDB Ref ID: 138965

• Personal Communication, 2014e, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; December 18, 2014, 11:00 AM EST; SRDB Ref 

ID: 139114

• Personal Communication, 2014f, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; December 11, 2014, 11:00 AM EST; SRDB Ref 

ID: 139115

• Personal Communication, 2014g, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; December 10, 2014, 11:00 AM EST; SRDB Ref 

ID: 139116

• Personal Communication, 2014h, Personal Communication with a Former Grand Junction 

Employee; Telephone Interview by ORAU Team; October 24, 2014, 9:00 AM MST; SRDB Ref 

ID: 139128
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

11 of 47 

4.5 NIOSH Site Research Database

NIOSH also examined its Site Research Database (SRDB) to locate documents supporting the 

assessment of the evaluated class. At the time when the initial SEC-00175 Evaluation Report was 

written, there were 603 documents in this database that were identified as pertaining to Grand 

Junction. Presently, there are 1,719 documents in the database pertaining to Grand Junction. These 

documents, particularly the more recent documents, were evaluated for their relevance to this petition. 

The documents include historical background on data types, monitoring, dust sampling, air 

monitoring, urinalysis data, fecal analysis, the radiological control program, medical monitoring, 

process materials, and process descriptions. 

5.0 Radiological Operations Relevant to the Class Evaluated by 

NIOSH

This present evaluation is for the time period at the Grand Junction Facilities from February 1, 1975 

through July 31, 2010. This section includes relevant discussions of the earlier years because those 

early operations would have likely resulted in residual contamination potentially impacting workers in 

later years. The following subsections, therefore, summarize radiological operations at the Grand 

Junction Facilities from 1943 through July 31, 2010, and the information available to NIOSH to 

characterize particular processes and radioactive source materials. From available sources NIOSH has 

gathered process and source descriptions, information regarding the identity and quantities of the 

radionuclides of concern, and information describing processes through which radiation exposures 

may have occurred and the physical environment in which they may have occurred. The information 

included within this SEC-00175 Evaluation Report Addendum is intended only to be a summary of 

the available information and a summary of evaluations that have been performed after the 

presentation of the original SEC-00175 Evaluation Report. 

5.1.1 Grand Junction General Operations

In 1943 the Manhattan Engineer District purchased the Grand Junction site. A refinery was operated 

on the site from 1943 to 1946 to treat and concentrate uranium oxide from "green sludge," a byproduct 

of vanadium production in the area. Approximately 1,180 tons of uranium oxide and a comparable 

amount of vanadium concentrate were produced and shipped offsite for further refining (WASTREN, 

2001b, PDF p. 15). 

Beginning in 1947, AEC operated a uranium concentrate sampling plant and assay laboratory on site. 

Between 1948 and 1971, a total of approximately 172,500 tons of uranium oxide and 14,500 tons of 

vanadium oxide passed through the facility in steel drums. The remaining stockpiled vanadium and 

uranium concentrates were shipped offsite in 1965 and 1975, respectively (WASTREN, 2001b, PDF 

p. 15). 

By February 1, 1975, concentrate sampling operations had ended and the site mission had changed to 

mainly off-site work (e.g., National Uranium Resource Evaluation (NURE) and Uranium Mill 

Tailings Remedial Action Project (UMTRA); although on-site work with uranium and thorium ores 

and mill tailings continued in the Sample Preparation Laboratory, Building 7A. 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

12 of 47

Building 7A was constructed as an addition to Building 7 in 1956. Reconstruction and remodeling of 

the facility took place during the period from 1978 through 1986 (WASTREN, 2001a). There were 

no renovations to the facility after 1986. 

Work in the Sample Preparation Laboratory included processing thousands of samples for analysis. It 

also involved numerous short-term processing efforts of uranium and thorium ores, and tailings used 

in the fabrication of calibration materials and pads. 

The Sample Preparation Laboratory (Building 7A) in Building 7 was the location with the highest 

potential for internal dose after January 31, 1975. The grinding, crushing, and preparation of these 

samples occurred in Building 7A. In March 2001, the sample preparation operations were moved to 

Building 46. Analytical chemistry operations ended in late 2003. Some sample preparation for offsite analysis was conducted in a small area of Building 32 until at least 2007. 

Instrument Calibration Models

From 1974 to 1984, Grand Junction supported the NURE Program, which was a nationwide uranium 

modeling effort. During this program, mainly non-ore samples (drilling cores, etc.) were collected 

from off-site locations. The samples were returned to the site for processing. Some of the samples 

were crushed, ground to the proper size, and blended in the sample preparation area in Building 7A, 

prior to analysis in the Analytical Chemistry Laboratory, Building 20. The sample preparation 

activities presented the greatest potential for internal exposures after the end of concentrate sampling 

and storage in January 1975.

Instrument calibration models, consisting of concrete mixed with radioactive materials, were 

constructed at Grand Junction over its history. The models were in the form of pads and boreholes. 

Models were developed to support the NURE program as well as the remediation programs. 

Thorium Models

Thorium was never routinely processed at Grand Junction. However, Th-232 was handled 

sporadically in relatively small quantities to develop the instrument calibration sources or models 

(pads and boreholes) for ore exploration and environmental remediation. Although the small amount 

of Th-232 present in the calibration models (approximately 40 kg) was orders of magnitude less than 

the tons of uranium ore, uranium concentrate, and uranium mill tailings handled on site, there still 

existed the potential for intakes of Th-232 during the 1975-1988 time period, particularly during 

thorium ore crushing and grinding operations in the Sample Preparation Laboratory.

NIOSH has identified at least twenty-seven calibration models containing thorium that were 

manufactured at Grand Junction between 1975 and 1985. Descriptions of these models, including 

details about the manufacturing process for some of them, can be found in various documents that are 

available to NIOSH (Mathews, 1978; Ward, 1978; Leino, 1994). The model manufacturing process 

generally involved crushing and grinding thorium ore to a specified mesh size and then blending it 

down to a much lower concentration with sand or some other non-radioactive diluents. For some of 

the thorium-containing models, monazite sand was the thorium starting material. This sand was of the 

proper mesh size and did not require crushing or grinding. The blended mixtures would then be 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

13 of 47

mixed uniformly with cement to form solid shapes. For the bore-hole type models the shapes were 

generally cylindrical, with dimensions of several feet wide by several feet deep, with a bore-hole 

drilled through the center that radiation detection probes could be lowered into for calibration. 

There were only two campaigns involving thorium that took place after 1985. The first of those 

campaigns is described in a 1987 report, Construction and Characterization of the TL/TH Thorium 

Calibration Pads (Steele, 1987). Four sets of thorium-232 containing pads were constructed (2 pads 

per set). Each set consisted of a high (TH) and a low (TL) pad. Each pad was 5-ft in diameter and 2-

ft tall, with a 3-inch diameter hole drilled horizontally through the center. The TH pads were 

approximately 45 pCi/g Th-232 and the TL pads were about 11 pCi/g. Their construction required 

approximately 200 pounds of thorium ore. The thorium concentration of the starting material (ore) 

was 7441 pCi/g (6.8% Th). This operation, at least the thorium handling part of the operation, was 

completed in 1986.

The only other thorium campaign taking place at Grand Junction after 1985 was the manufacture of 

soil-based uranium disequilibrium and mixed uranium-thorium series radionuclide reference materials 

(Donivan, 1988). The operation was completed in 1988. Two sets of radionuclide reference materials 

were prepared for use by remedial action contractors and cognizant Federal and State agencies. A 

total of six reference materials, two sets comprising three reference materials each, were prepared with 

varying concentrations of radionuclides using mill tailings materials, ores, and a river-bottom soil 

diluent. One set (disequilibrium set) contains varying amounts of uranium with nominal amounts of 

radium-226. The other set (mixed-nuclide set) contained varying amounts of U-238 and Th-232 

decay series nuclides. All materials were ground, dried, and blended thoroughly to ensure 

homogeneity. A total of 7.8 kg of thorium ore starting material was used for this operation. 

Uranium Models

In addition to the calibration models containing thorium, as described in the discussion above, very 

similar calibration models were also prepared which contained uranium. Generally speaking, 

whenever thorium models were manufactured, companion models containing uranium were also 

manufactured during the same time period. The starting material for the uranium models was highgrade uranium ore (5-10% U3O8) or uranium mill tailings. Like the thorium model production 

operations, grinding and crushing of uranium ore (or tailings) was necessary to produce the uranium 

models.

5.2.1 Internal Radiological Exposure Sources from Grand Junction Operations

Inhalation and ingestion of uranium- and thorium-ore dust and uranium-concentrate dust generated

during the preparation of samples for analysis, and in the manufacture of calibration models and 

reference materials, were the primary sources of internal exposure for Grand Junction workers after 

January 1975.

5.2.1.1 Uranium

The most radiologically hazardous on-site work after January 1975 appears to have taken place in the 

sample preparation area of Building 7. A 1980 environmental monitoring report (Environmental 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

14 of 47

Monitoring, 1980) stated that the Sample Plant prepared approximately 1000 samples per month, but 

that the majority of the samples were not uranium ores but were exploration samples of low 

radioactivity. It indicated that the principal environmental problem was the dust generated from 

grinding and crushing. The report also states that occasionally, very high-grade uranium or thorium 

ore (5-10 percent U3O8 or ThO2) were handled in the preparation of calibration models. This 

operation could produce dust which exceeded the uranium-in-dust standard. The relevant American 

Conference of Government and Industrial Hygienists (ACGIH) standard at the time was 0.2 mg/m3 of 

uranium.

5.2.1.2 Thorium

Thorium ore and thorium-containing monazite sand were occasionally used in the construction of 

instrument calibration models (see Section 5.1.1 above). Crushing and grinding thorium ore during 

these activities would have resulted in a potential airborne thorium hazard (Environmental 

Monitoring, 1980). 

6.1 Available Grand Junction Internal Monitoring Data

Bioassay Data

When the Grand Junction site was established, it was recognized that bioassay may be required for 

personnel “directly exposed to special materials” (Ruhoff, 1943). However, there is no 

comprehensive database of bioassay results for the Grand Junction site. A limited number of bioassay

results are contained in documents captured by NIOSH for the period 1945 through 1999, as shown in 

Table 6-1.

There are samples from 1984 to 1986 (Bioassay, Jan1984-Dec1986). These samples, however, are 

primarily identified as initial (baseline) samples, and most are for off-site remediation workers, 

making the data irrelevant for estimating on-site intakes. These were urine and fecal samples which 

were generally analyzed by alpha spectroscopy. The samples were typically analyzed for U234/235/238, but often included Th-230 and Ra-226. There are also fecal bioassay data for some 

workers who were performing grinding operations with uranium mill tailings in the Sample 

Preparation Laboratory (Bioassay, Apr1985-Mar1987). The samples collected for the post-1975 

period were for both off-site and on-site work. Therefore, for a given worker, the samples might not 

be for work that is covered by EEOICPA. For part of this period, there was a pre-job sampling 

program, and many of the samples were collected for this purpose. After 1990, the practice was to 

collect pre-job samples but discard them after a period (about one year) if the worker had not been 

exposed to greater than 10% of a DAC or 40 DAC-hours. There is some duplication of the data 

available to NIOSH. Data were sometimes re-sent by the contract laboratories due to reanalyzed 

samples, etc. Some sample collection dates are missing in the references. Some of the gaps in 

bioassay data might represent periods of little activity. For example, the Grand Junction Project 

Office Remedial Action Program (GJPORAP) started in 1984, when initial surveys and assessments 

were completed. The actual period of decontamination and decommissioning (D&D) work did not

begin until 1988, with the “extensive” decontamination of Buildings 33 and 35 (Vanderheiden, 1993) 

and the start of the remediation of the outdoor tailings contamination. 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

15 of 47

Within Table 6-1, it should be noted that there is some overlap in the references and that some of the 

early results are not very legible. The small number of results captured to date is due to two factors: 

(1) only a relatively small number of workers on site directly handled the radioactive materials; 

workers were sampled based on perceived likelihood of intakes (just as workers are sampled under 

current DOE standards); and (2) the captured data are from general site records rather than individual 

exposure records (which would likely represent a more complete dataset). 

A review of the claimants in NIOSH’s database indicates that some workers do have bioassay 

measurements included in their records; however, there are not enough claimants with bioassay 

information available to indicate which workers were routinely included in a bioassay program.

Initially, urine samples were analyzed for total uranium by fluorometric methods by the AEC New 

York Operations Office Health and Safety Laboratory. It appears that bioassay samples were 

subsequently analyzed on site, but the dates are unclear. In 1971, the sampling plant was shut down 

(GJ Contractors, undated), and by early 1975, the remaining drums of uranium concentrate stored on 

site were shipped out. While analytical laboratory operations continued, the source term for most 

workers was then reduced to residual building and environmental contamination. The on-site 

analytical laboratory did not accept high-activity samples, and the workers were not required to be in a 

bioassay program (Personal Communication, 2010h). Bioassay requirements were determined on a 

case-by-case basis by the Health and Safety Plan that governed the specific decontamination and 

decommissioning project (Henwood, 1986; Personal Communication, 2010c). A site procedure 

entitled Internal Radiation Dosimetry Program was revised in 1990 to comply with DOE Order 

5480.11; the revision required weekly samples for subcontractors and monthly samples for site 

employees if they were working in an Airborne Radioactivity Area (Procedure, 1990).

Table 6-1: Grand Junction Office Bioassay Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results Company/Organization SRDB Ref IDs Notes

1945 11 GJ Mill (Refinery) 16855 U in urine, 1 seta in Jun

1949 7 None shown 3306 U in urine, all from Dec.

1953 11 American Cyanamid 6645 U in urine, 2 sets - Jul and Dec

1953 4 American Cyanamid 11452 U in urine, 1 set in Dec

1953 32 American Smelting 3319 U in urine, 3 sets Feb, May, and Sep

1953 22 American Smelting 11452 U in urine, 2 sets - Feb and May

1954 10 American Cyanamid 6645 U in urine, 2 sets - Feb and Jul

1954 10 American Cyanamid 11452 U in urine, 2 sets - Feb and Jul

1954 24 American Smelting 3319 U in urine, 2 sets - Jan and Nov

1954 13 American Smelting 11452 U in urine, 2 sets - Jan and May

1956 66 Lucius Pitkin 3307, 3397 U in urine; 3 sets - May, Jun, and Oct

1956 1 None shown 76923 U in urine; result reported Aug 0.009 mg/l

1956 1 None shown 76924 U in urine; result reported Jul 0.078 mg/l

1956 47 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1957 49 Lucius Pitkin 3307, 3397 U in urine; 2 sets - May and Oct

1957 49 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1958 25 Lucius Pitkin 3307, 3397 U in urine, 1 set - Jun
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

16 of 47

Table 6-1: Grand Junction Office Bioassay Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results Company/Organization SRDB Ref IDs Notes

1958 29 Lucius Pitkin 11451 U in urine, 1 set in Dec

1958 1 None shown 76938 One "composite" U in urine sample, 0.016 mg/l 

from Feb

1958 1 None shown 76940 U in urine; one sample, 0.032 mg/l from Jan

1958 63 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1959 31 Lucius Pitkin 3307, 3397 U in urine, 1 set - Jun; plus 1 Aug result

1959 28 Lucius Pitkin 11451 U in urine, 1 set in Dec

1959 59 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1960 49 Lucius Pitkin 3307, 3397 U in urine, 2 sets - Jun and Dec

1960 49 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1961 57 Lucius Pitkin 3307, 3397

U in urine; 2 sets - Jun and Dec; plus 2 Jan 

results and 1 Mar result.

1961 58 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1962 26 Lucius Pitkin 3307, 3397 U in urine, 1 set - Jun; plus 1 Jan result

1962 49 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1963 44 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1964 See Notes Lucius Pitkin 14442 Annual report for 1964. 8 employees sampled 

in Jul and Dec. One additional in Dec. Results 

were in the range from 0.008 to 0.021 mg/l, 

below the reference pointb (RP) of 0.05 mg/l.

1964 10 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1965 47 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1966 64 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1967 71 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1968 70 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1969 See Notes Lucius Pitkin 13800 Annual report for 1969. In Mar, 23 samples 

were collected. All were below the reference 

point of 0.025 mg/l with 4 exceptions who were 

re-sampled. In Oct, 17 samples were collected 

and all were below the RP with again 4 

exceptions. Re-sampling showed 3 of 4 were 

below. Two employees are listed by name with 

results of 0.054 and 0.077 mg/l.

1969 55 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1970 27 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1971 30 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1972 See Notes Lucius Pitkin 13802 Annual report for 1972. No. of samples not 

given, but all were in the range of 0.001 to 

0.008 mg/l.

1972 11 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1973 See Notes Lucius Pitkin 13803 Annual report for 1973. No. of samples not 

given, but all were in the range of 0.001 to 

0.056 mg/l.

1973 52 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11

1974 14 Lucius Pitkin 98104 Urinalysis Report, collected 5/24/11
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

17 of 47

Table 6-1: Grand Junction Office Bioassay Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results Company/Organization SRDB Ref IDs Notes

1984 1 Bendix 97742 Exposure history for specific individual, 

collected 5/23/11

1984 1 Bendix 97813 Exposure history for specific individual, 

collected 5/25/11

1984-

1986

1589 Bendix 98107 Urinalysis Sampling Log, collected 5/24/11

1986 16 INEL 97808 Bioassay Report for Grand Junction, collected 

5/21/11

1986 8 UNC Technical Services 98096 Bioassay Report for Grand Junction, collected 

5/24/11

1986 8 INEL 125901 Bioassay Report for Grand Junction, collected 

5/24/11

1990 2 Lawrence Livermore 

National Laboratory

97808 Internal Dose Assessments for 1990, collected 

5/21/11

1990 133 Thermo Analytical 97828 Radiological Analysis Results for Ra in urine, 

collected 5/24/11

1990 109 GeoTech 97828 1990 Bioassay Results, collected 5/24/11

1991 8 Thermo Analytical 97828 Radiological Analysis Results in urine, 

collected 5/24/11

1991 20 Thermo Analytical 97847 Radiological Analysis Results in urine, 

collected 5/24/11

1991 20 Thermo Analytical 97849 Radiological Analysis Results in urine, 

collected 5/24/11

1991 6 Thermo Analytical 97851 Radiological Analysis Results in urine, 

collected 5/24/11

1991 43 Thermo Analytical 97852 Radiological Analysis Results in urine, 

collected 5/24/11

1991 30 Thermo Analytical 97854 Radiological Analysis Results in urine, 

collected 5/24/11

1991 30 Thermo Analytical 97856 Radiological Analysis Results in urine, 

collected 5/24/11

1991 5 Thermo Analytical 97857 Radiological Analysis Results in urine, 

collected 5/24/11

1991 8 Thermo Analytical 97858 Radiological Analysis Results in urine, 

collected 5/24/11

1991 1 GeoTech 97637 Exposure history for specific individual, 

collected 5/23/11

1991 1 GeoTech 97679 Exposure history for specific individual, 

collected 5/23/11

1991 22 Thermo Analytical 97838 Radiological Analysis Results in urine, 

collected 5/24/11

1991 18 Thermo Analytical 97839 Radiological Analysis Results in urine, 

collected 5/24/11
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

18 of 47

Table 6-1: Grand Junction Office Bioassay Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results Company/Organization SRDB Ref IDs Notes

1991 11 Thermo Analytical 97842 Radiological Analysis Results in urine, 

collected 5/24/11

1991 5 Thermo Analytical 97843 Radiological Analysis Results in urine, 

collected 5/24/11

1991 13 Thermo Analytical 97871 Radiological Analysis Results in urine, 

collected 5/24/11

1991 20 Thermo Analytical 97878 Radiological Analysis Results in urine, 

collected 5/24/11

1991 24 Thermo Analytical 97880 Radiological Analysis Results in urine, 

collected 5/24/11

1991 20 Thermo Analytical 97882 Radiological Analysis Results in urine, 

collected 5/24/11

1991 65 Thermo Analytical 97883 Radiological Analysis Results in urine, 

collected 5/24/11

1991 20 Thermo Analytical 97884 Radiological Analysis Results in urine, 

collected 5/24/11

1991 27 Thermo Analytical 97885 Radiological Analysis Results in urine, 

collected 5/24/11

1991 20 Thermo Analytical 97886 Radiological Analysis Results in urine, 

collected 5/24/11

1991 7 Thermo Analytical 97887 Radiological Analysis Results in urine, 

collected 5/24/11

1991 32 Thermo Analytical 97888 Radiological Analysis Results in urine, 

collected 5/24/11

1991 1 Thermo Analytical 97889 Radiological Analysis Results in urine, 

collected 5/24/11

1991 63 Thermo Analytical 97890 Radiological Analysis Results in urine, 

collected 5/24/11

1991 31 Thermo Analytical 97891 Radiological Analysis Results in urine, 

collected 5/24/11

1991 24 Thermo Analytical 97892 Radiological Analysis Results in urine, 

collected 5/24/11

1991 49 Thermo Analytical 97893 Radiological Analysis Results in urine, 

collected 5/24/11

1991 49 Thermo Analytical 97894 Radiological Analysis Results in urine, 

collected 5/24/11

1991 49 Thermo Analytical 97895 Radiological Analysis Results in urine, 

collected 5/24/11

1991 49 Thermo Analytical 98090 Radiological Analysis Results in urine, 

collected 5/24/11

1991-

1992

139 GeoTech 97763 Radon log in sheets, collected 5/24/11

1992 15 Chem-Nuclear Geotech 97762, 97809 Internal Dose Assessments for 1992, collected 

5/21/11
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

19 of 47

Table 6-1: Grand Junction Office Bioassay Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results Company/Organization SRDB Ref IDs Notes

1992 7 GeoTech 97792 Memo about bioassay results and recommended 

follow-up testing, collected 5/23/11

1992 28 GeoTech 97784 Evaluation of Uranium Oxide Spill, collected 

5/23/11

1992 18 Thermo Analytical 97841 Radiological Analysis Results in urine, 

collected 5/24/11

1995 12 RUST Geotech 97828 Internal Radiation Dose Assessment for 

Individuals Visiting, collected 5/24/11

1995 7 RUST Geotech 90511 7 fecal samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U)

1995 10 RUST Geotech 90512 10 urine samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U, Th-230, and Ra-226).

1995 18 RUST Geotech 90513 18 urine samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U, Th-228/230, and Ra-226).

1995 7 RUST Geotech 90514 7 fecal samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis. 4 Pu/Am and 3 U for 6 personnel 

(one had both)

1995 10 RUST Geotech 90515 10 urine samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U)

1995 12 RUST Geotech 90516 12 urine samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U, Th-230, and Ra-226)

1995 10 RUST Geotech 90517 10 urine samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U), collected 10/3/95

1996 11 MACTEC 90528 11 fecal samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U)

1997 12 MACTEC 90528 12 fecal samples sent to Teledyne Brown

Engineering Environmental Services for alphaspec analysis (U)

1997 9 MACTEC 90508 9 post-job fecal samples collected 5 days after 

potential exposure; sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U). Additional urine and fecal 

baseline results on pdf p. 65

1997 45 MACTEC 90510 45 urine samples sent to Lockheed-Martin 

Idaho Lab in 1997. Total U results in μg/l.

1997 10 MACTEC 90523 10 urine samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U), collected 1/6/97

1997 11 MACTEC 90524 11 fecal samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U), collected 11/12/97
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

20 of 47

Table 6-1: Grand Junction Office Bioassay Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results Company/Organization SRDB Ref IDs Notes

1997 11 MACTEC 90525 11 fecal samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U), collected 11/12/97

1997 9 MACTEC 90526 9 fecal samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U), collected 11/12/97

1997 10 MACTEC 90527 10 urine samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U), collected 4/1/97

1997 23 MACTEC 90528 23 fecal samples sent to Teledyne Brown 

Engineering Environmental Services for alphaspec analysis (U), collected 11/11/2010

1998 6 MACTEC 90507 4 urine samples collected in June 1998 sent to 

Lockheed Martin Idaho Technologies Company 

Bioassay Laboratory for total U as the result of 

an off-site incident (facial contamination from 

windblown tailings at Monticello). 2 fecal 

samples collected in September 1998 and 

analyzed for isotopic U following demolition 

work at the GJO site.

1999 670 MACTEC 90509 Radon personal dosimeter data for individuals 

using Landauer “DRNT” detector (track 

detector). Two quarterly periods and one semiannual period. Exposures reported in pCi/ldays. Of the total, 24 were area monitors.

Notes:

a A “set” is a group of samples taken at approximately the same time. b A definition of “reference point” was not located. Workers above the reference point were re-sampled. 

Air Monitoring Data

In December 1985, three high-volume air samplers were installed on the site; air concentrations of 

uranium, Th-230, and Ra-226 are reported in annual environmental reports for 1986 through 1993 

(Environmental Monitoring, 1986; Environmental Monitoring, 1987; Environmental Monitoring, 

1988; Environmental Monitoring, 1989; Environmental Monitoring, 1990; Environmental Monitoring, 

1991; Environmental Monitoring, 1992; Environmental Monitoring, 1993). Radon measurements are 

available in the annual environmental reports for 1987 through 1993. 

In a 1986 memorandum, with the subject line “Summary of MPC-Time Weighted Exposure for the 

First Quarter,” air monitoring results for [Redacted per Privacy Act] individuals performing grinding 

of uranium mill tailings are presented (Rothman, 1986). The results from these samples are presented 

in units of MPC-HRS/QTR (maximum permissible concentration-hours per quarter). Under worstcase assumptions, the maximally exposed individual received 307 MPC-HRS of exposure to soluble 

Th-230. The respirators that were worn for these individuals were assumed by NIOSH to provide 

zero protection. In the memorandum, the sample results were compared to allowable MPC-hours 

(Rothman, 1986). Because the samples were collected over an entire quarter, NIOSH considers these 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

21 of 47

data to be representative of grinding and crushing tailings in the Sample Preparation Laboratory. 

These data are also supported by bioassay data taken during the work (Bioassay, Apr1985-Mar1987). 

Prior to the start of the D&D work in 1989, air sample data are scarce. The most radiologically 

hazardous on-site work at that time appears to have taken place in the sample preparation area. A 

1980 environmental monitoring report stated that the Sample Plant prepared approximately 1000 

samples per month, but that the majority of the samples were not uranium ores but were exploration 

samples of low radioactivity. It indicated that the principal environmental problem was the dust 

generated from grinding and crushing. The report also mentions air sampling being performed in the 

Sample Plant during July 1980 while ore samples were being prepared. The most concentrated 

sample contained 0.0046 mg/m3 of uranium (Environmental Monitoring, 1980). The report indicates 

that the relevant ACGIH standard at the time was 0.2 mg/m3 of uranium. The report also states that 

occasionally, very high-grade uranium or thorium ore (5-10 percent U3O8 or ThO2) was handled in the 

preparation of calibration models. This operation could produce dust which exceeds the uranium-indust standard.

In a March 1990 document titled Technical Basis for Bioassay Sampling for Sample Preparation 

Plant and Grand Junction Vicinity Property Workers, a set of air monitoring data are presented for the 

Sample Preparation Laboratory (UNC Geotech, 1990, PDF p. 9). The data consist of isotopic air 

concentration measurements for Po-210, Ra-226, Th-230, Pb-210, U-238, and Bi-210. The data from 

these measurements are evaluated in the document whereby it is shown that Th-230 contributes to 

over 90% of the overall Committed Effective Dose Equivalent (CEDE) of the radionuclide mixture. 

Five hundred and sixty-nine air sample measurements were recovered for on-site D&D work, post1988, including both general area and breathing zone samples (Building 7 H&S Data, 1991-2001; Air 

Sampling, Nov-Dec1990; Building 12 H&S Data, 1991-2000; Building 18 H&S Data, 1991-2001;

Building 20 H&S Data, 1990-2000; Building 28 H&S Data, 1986-2000; Building 31/31A H&S Data, 

1990-1992; Building 36 H&S Data, 1992-1996; Building 938 H&S Data, 1993-1999; Building 3022 

H&S Data, 1980-2000; Building 7A H&S Data, 1991-2001; Building 7A H&S Data, 2001; Building 7 

H&S Data - Phase II, 1980-2000; Building 7 H&S Data - Phase I, 1972-1999; D&D Reports, 1985-

1999). These samples indicate that air concentrations were well-controlled during these activities 

(generally less than 10% of the DAC or action level in use). 

The annual atmospheric releases of radioactive materials are available for most years from 1992 

through 2001. These reports indicated that very low levels were released; therefore, the on- and offsite concentrations would have been relatively low. The air monitoring data are summarized in Table 

6-2. For the D&D period (1986-2001), numerous other examples of air monitoring, including 

breathing zone samples, have been located. For example, the remediation of Building 7, which was 

contaminated during use for sample preparation, was divided into three phases (areas). There were 60 

area measurements and 15 personnel measurements made in Building 7 just in Phase III (Airborne 

Radioparticulates, 1994). Most of these measurements were made following a 1994 contamination 

incident caused by a water leak, and during removal of contaminated concrete in 1999. Other building 

health and safety data files contain similar air monitoring data (Building 11 H&S Data, 1993-1997; 

Building 12 H&S Data, 1991-2000; Building 18 H&S Data, 1991-2001; Building 20 H&S Data, 

1990-2000; Building 26 H&S Data, 1980-1998; Building 28 H&S Data, 1986-2000; Building 29 H&S 

Data, 1997; Building 31/31A H&S Data, 1990-1992; Building 36 H&S Data, 1992-1996; Health and 

Safety Checklists, 1990-1991).
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

22 of 47

Table 6-2: Grand Junction Office Air Monitoring Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results

Area/Company/

Organization

SRDB Ref 

IDs Notes

1945 3 GJ Mill (Refinery) 16855 All results below 25 μg/m3; collected in 

Jun

1945 3 GJ Warehouse Area 16855 2 results above 25 μg/m3

1945 2 Sampling Lab 16855 All results below 25 μg/m3

1953 10 American Cyanamid 6650 Samples taken in May, Jul, and Aug. 3 

samples in May are in terms of alpha 

counts/m3

.

1954 1 American Cyanamid 6650 Sample from Jun

1956 64 Lucius Pitkin 3307, 3397 Results appear to be GA; Jun and Sep; 

some are BZ samples

1956 6 Lucius Pitkin 3307, 3397 Results appear to be Ra; Ra analysis on 

some GA samples

1956 3 Lucius Pitkin 3337 Report in July of "high" air samples in 

auger sampling room; no concentrations 

given in this report but probably are 

those used for comparison with 1959 

samples in 3343.

1956 See Notes Lucius Pitkin 3393 Report not attached. Summarized as "In 

the initial sampling room the air 

samples were between 200 and 400

d/p/m3

. In the blender room they were 

of the order of 2,000." Probably 

included in 3307/3397.

1956 See Notes National Lead 3382 Report not attached. Summarized as "of 

the 79 employees who were studied, all 

but [Redacted per Privacy Act] had 

exposures which were less than 50 

d/m/m3

. Only [Redacted per Privacy 

Act] of the remaining [Redacted per 

Privacy Act] had a really significant 

exposure. [Redacted per Privacy Act] 

was exposed to uranium dust in a 

concentration of approximately 250 

mg/m3 (350 d/m/m3)."

1956 79 National Lead 10241 Samples from Jul and Sep

1957 25 National Lead 10241 Samples from Apr and Sep

1959 14 Lucius Pitkin 3307, 3397 Results appear to be GA; Nov

1959 3 Lucius Pitkin 3343 22 samples taken in Aug by Grand 

Junction. Only three results were 

reported by NYOO in terms of 

concentrations

1959 22 Sampling Plant, Lucius 

Pitkin

11452 Samples from Aug

1960 28 Falling Stream Pilot Plant, 

Lucius Pitkin

3307, 3397 Results appear to be GA; Jun and Jul

1960 41 Grand Junction (general) 11452 Samples from Jun and Jul - Outside 

areas (environmental-type)

1961 12 Grand Junction (general) 11452 Samples from Nov - Outside areas 

(environmental-type)
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

23 of 47

Table 6-2: Grand Junction Office Air Monitoring Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results

Area/Company/

Organization

SRDB Ref 

IDs Notes

1961 80 Sampling Plant, LuciusPitkin3307, 3397 Results appear to be GA; Jun (most) 

and Sep

1967 5 Grand Junction AEC 

Compound

17031 Rn-222 levels in pCi/l; Jul, Sep, Oct, 

and Nov; included in 17034

1967 7 Grand Junction AEC 

Compound

17034 Rn-222 levels in pCi/l; Jul, Sep, Oct, 

Nov, and Dec

1967 16 Grand Junction (general) 82790 Radon levels in GJ area 1967-1968; 16 

measurements are for one station in or 

near the AEC compound.

1968 9 Grand Junction (general) 17034 Rn-222 levels in pCi/l; Jan, Feb, Mar, 

Apr, Jun, and Aug

1986 See Notes Grand Junction (general) 90851 Annual Environmental Report with 

particulate monitoring results for three 

stations.

1986 See Notes Grand Junction (general) 29855 Statement that there are "no significant 

radionuclide emissions from GJPO 

facilities including the laboratories, 

sample preparation facility, and the 

radon chamber."

1986 300 Grand Junction (in doors) 6640 100 radon-daughter-concentration 

(RDC) measurements in each of Bldgs. 

33, 34, and 35. RDCs averaged 0.0051, 

0.177and, 0.0069 WL, respectively with 

0 percent thoron.

1986 3 Grand Junction (in doors) 98100 MPC-time weighted exposure for first 

quarter 1986. Measurements taken in 

sample prep lab during time of grinding 

of uranium mill tailings.

1987 See Notes Grand Junction (general) 90847 Annual Environmental Report with 

particulate monitoring results for three 

stations (total U, Th-230, Ra-226); 

radon monitoring results for three 

stations.

1988 See Notes Grand Junction (general) 90846 Annual Environmental Report with 

particulate monitoring results for three 

stations (total U, Th-230, Ra-226); 

radon monitoring results for three 

stations.

1989 See Notes Grand Junction (general) 90856 Annual Environmental Report with 

particulate monitoring results for four 

stations (total U, Th-230, Ra-226); 

radon monitoring results for three 

stations.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

24 of 47

Table 6-2: Grand Junction Office Air Monitoring Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results

Area/Company/

Organization

SRDB Ref 

IDs Notes

1989 569 Grand Junction (general) 89872, 89909, 

89926, 89931, 

89938, 89979, 

89991, 90015, 

90087, 90105, 

90118, 90154, 

90155, 90164, 

93709

Air sample measurements for on-site 

D&D work, post-1988, including both 

general area and breathing zone 

samples.

1990 See Notes Grand Junction (general) 90845 Annual Environmental Report with 

particulate monitoring results for four 

stations (total U, Th-230, Ra-226); 

radon monitoring results for three 

stations.

1990 1 Grand Junction (general) 37700 Annual atmospheric release of 

radioactive material

1990 16 Grand Junction (in doors) 100231 Technical basis document for internal 

dosimetry. Includes isotopic air 

concentration measurements for Bldg. 

7A Sample Prep Laboratory.

1991 See Notes Grand Junction (general) 90853 Annual Environmental Report with 

particulate monitoring results for four 

stations (total U, Th-230, Ra-226); 

radon monitoring results for eight 

stations.

1991 1 Grand Junction (general) 37700 Annual atmospheric release of 

radioactive material

1991 30 Grand Junction (in doors) 13191 Results of the DOE indoor radon study; 

19 occupied buildings measured.

1992 See Notes Grand Junction (general) 90860 Annual Environmental Report with 

particulate monitoring results for three

stations (total U, Th-230, Ra-226); 

radon monitoring results for seven 

stations.

1992 1 Grand Junction (general) 37700 Annual atmospheric release of 

radioactive material

1993 See Notes Grand Junction (general) 90857 Annual Environmental Report with 

particulate monitoring results for three 

stations (total U, Th-230, Ra-226); 

radon monitoring results for seven 

stations.

1993 1 Grand Junction (general) 37700 Annual atmospheric release of 

radioactive material

1994 1 Grand Junction (general) 37700 Annual atmospheric release of 

radioactive material

1996 1 Grand Junction (general) 76642 Annual atmospheric release of 

radioactive material

1998 1 Grand Junction (general) 44873 Annual atmospheric release of 

radioactive material
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

25 of 47

Table 6-2: Grand Junction Office Air Monitoring Data in the Site Research Database

(This table spans multiple pages)

Year Approx. No. 

of Results

Area/Company/

Organization

SRDB Ref 

IDs Notes

1999 1 Grand Junction (general) 44873 Annual atmospheric release of 

radioactive material

2000 1 Grand Junction (general) 44873 Annual atmospheric release of 

radioactive material

2001 1 Grand Junction (general) 44873 Annual atmospheric release of 

radioactive material

6.2 Available Grand Junction Operations External Monitoring Data

Exposure records are maintained at the Grand Junction office and in a database maintained by the 

Idaho National Laboratory (INL). Since the issuance of the initial SEC-00175 Evaluation Report, a 

data report was provided by INL that includes personnel believed to be associated with Grand 

Junction through the use of INL location codes (Dosimetry, 1986-2007). This report has data between 

the years 1982 and 1998 and contains over 15,000 records, each with a gamma and beta result. There 

are also occasional neutron results in this spreadsheet. The people listed in this report may include 

individuals involved in off-site remediation work. As a claimant-favorable assumption, all exposures 

listed in this report would be assumed to have occurred on the Grand Junction Facilities site.

A series of 25 files are available to NIOSH from Grand Junction that comprises dosimetry files. Each 

file contains documents for people whose last names begin with an A, B, C, etc. (some dosimetry data 

may be found in these files).

Note: Table 6-7 is a new table that is not in the original SEC-00175 Evaluation Report. This table 

does not replace an existing table in the SEC-00175 Evaluation Report.

Table 6-7: External Dosimetry Files

(This table spans multiple pages.)

SRDB Reference Filename

102153 Dosimetry Files for Employees Last Name Starting With A

102195 Dosimetry Files for Employees Last Name Starting With B

102208 Dosimetry Files for Employees Last Name Starting With C

102229 Dosimetry Files for Employees Last Name Starting With D

102231 Dosimetry Files for Employees Last Name Starting With E

102233 Dosimetry Files for Employees Last Name Starting With F

102242 Dosimetry Files for Employees Last Name Starting With G

102343 Dosimetry Files for Employees Last Name Starting With H

102391 Dosimetry Files for Employees Last Name Starting With I

102393 Dosimetry Files for Employees Last Name Starting With J

102152 Dosimetry Files for Employees Last Name Starting With K

102158 Dosimetry Files for Employees Last Name Starting With L

102232 Dosimetry Files for Employees Last Name Starting With M
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

26 of 47

Table 6-7: External Dosimetry Files

(This table spans multiple pages.)

SRDB Reference Filename

102410 Dosimetry Files for Employees Last Name Starting With N

102415 Dosimetry Files for Employees Last Name Starting With O

102472 Dosimetry Files for Employees Last Name Starting With P

102506 Dosimetry Files for Employees Last Name Starting With Q

102416 Dosimetry Files for Employees Last Name Starting With R

102450 Dosimetry Files for Employees Last Name Starting With S

102469 Dosimetry Files for Employees Last Name Starting With T

102151 Dosimetry Files for Employees Last Name Starting With U

102154 Dosimetry Files for Employees Last Name Starting With V

102155 Dosimetry Files for Employees Last Name Starting With W

102156 Dosimetry Files for Employees Last Name Starting With Y

102157 Dosimetry Files for Employees Last Name Starting With Z

Interviews with current workers indicate that there is no external monitoring currently (i.e., in 2010) 

performed for Grand Junction employees (Personal Communication, 2010b; Personal 

Communication, 2010d).

7.2 Evaluation of Bounding Internal Radiation Doses at Grand Junction

The principal sources of internal radiation doses after January 31, 1975, included potential inhalation 

and ingestion of natural uranium and thorium, and their associated progeny, resulting from ore 

crushing, grinding, and handling operations in the Sample Preparation Laboratory. The following 

subsections address the ability to bound internal doses, methods for bounding doses, and the 

feasibility of internal dose reconstruction.

7.2.1 Evaluation of Bounding Process-Related Internal Doses

The following subsections summarize the extent and limitations of information available for 

reconstructing the process-related internal doses of members of the class under evaluation.

7.2.1.1 Urinalysis Information and Available Data 

As shown in Table 6-1, uranium urine and fecal samples for 1943-1999 have been captured from site 

and DOE records. The urinalysis program targeted workers who were directly exposed to the uranium 

ores and concentrates. Data have been captured for the operation of the refinery, the Small Pilot Plant, 

and the Sampling Plants. No urine bioassay data have been captured for the Large Pilot Plant.

Some urinalysis and fecal analysis data for on-site remediation activities from 1986 through 2001 

have been recovered. These data are from contractor bioassay laboratories; the data packages include 

quality assurance data and information.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

27 of 47

7.2.1.2 Fecal Samples

Some fecal data for on-site remediation activities from 1986 through 2001 have been recovered. 

These data are from contractor bioassay laboratories; the data packages include quality assurance data 

and information.

7.2.1.3 Airborne Levels

Air sample results have been recovered from site and DOE records for 1945-1993. The details are

shown in Table 6-2. In 1985, 100 radon-daughter-concentration (RDC) measurements were located 

for each of three buildings that had once been used to process uranium. There are two sets of data, 

one from 1986 (Rothman, 1986) and one from 1990 (UNC Geotech, 1990), with uranium-in-air 

measurement results from the Sample Preparation Laboratory (Building 7A) during crushing and 

grinding operations. Thirty radon measurements were made of 19 buildings in 1989-1990 as a part of 

the DOE Indoor Radon Study (Radon, 1989-1990, pdf pp. 153-154). During remediation, Grand 

Junction documents frequently cite the data from the DOE Indoor Radon Study in terms of Working 

Level (WL), assuming a typical indoor equilibrium factor of 0.5. Other WL measurements in 1989 

for Buildings 6 and 31, and in 1997-1998 for Buildings 7, 28, 30, 31A, 32, 54, and 810 were located 

in the available characterization data presented in NIOSH’s 2011 SEC-00175 Evaluation Report

(NIOSH, 2011). There was an extensive air sampling program during the D&D of the site buildings,

including breathing zone samples (Airborne Radioparticulates, 1994).

7.2.3 Methods for Bounding Internal Dose at Grand Junction

7.2.3.1 Methods for Bounding Operational Period Internal Dose

NIOSH finds it is not feasible to estimate internal dose with sufficient accuracy for all workers on site 

from February 1, 1975 through December 31, 1985. There is insufficient information to estimate 

intakes of uranium and thorium (and associated progeny) until January 1, 1986. Although NIOSH 

found that it is not possible to completely reconstruct radiation doses for the proposed class, NIOSH 

intends to use any internal monitoring data that may become available for an individual claim (and 

that can be interpreted using existing NIOSH dose reconstruction processes or procedures). 

Therefore, dose reconstructions for individuals employed at Grand Junction Facilities during the 

period from February 1, 1975 through December 31, 1985, but who do not qualify for inclusion in the 

SEC, may be performed using these data as appropriate.

Bounding Uranium Inhalation Intakes from January 1, 1985 through July 31, 2010

By February 1, 1975, concentrate sampling operations had ended and the site mission had changed to 

mainly off-site work (e.g., NURE, UMTRA). Some workers occupied areas that had been used for 

sampling operations (e.g., converted to office space). The area contained mainly fixed contamination, 

but there was loose contamination in some overhead spaces, in walls, and in areas that were normally 

unoccupied. The workers were mainly exposed to residual yellowcake contamination. While some of 

the process buildings from the Large Pilot Plant were still on site (Buildings 31, 33, 34, and 35), they 

were generally unoccupied and used for storage (D&D Report, 1995, pdf, p. 15). Some workers 

continued to be exposed to radioactive materials during sampling preparation, laboratory operations, 

waste processing, etc. This work included processing thousands of samples for analysis. It also 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

28 of 47

involved numerous short-term processing efforts of uranium and thorium ores, and tailings used in the 

fabrication of calibration materials and pads. The grinding and crushing of the samples and ores was 

performed in the Sample Preparation Laboratory in Building 7A (part of Building 7); the 

downblending of processed ores used in the calibration models was also performed in Building 7.

Grinding and crushing samples and the ores and tailings used in the calibration models had the 

greatest potential for worker intakes. Limited monitoring data is available from those activities. 

Grand Junction performed air sampling in July 1980 during crushing and grinding ore samples and 

reported the highest measured result of 0.0046 mg/m3 (3.1 pCi/m3) (Environmental Monitoring, 

1980). No other data are available until 1986 when Sample Preparation Laboratory workers were 

monitored by tracking MPC-Hr exposure and by fecal bioassay. Additional monitoring data were 

reported in 1991. In 1991 the site implemented a more rigorous air monitoring and bioassay program.

The Sample Preparation Laboratory in Building 7 was the location having the highest potential for 

internal dose after January 31, 1975. The grinding, crushing, and preparation of these samples 

occurred in Building 7A. In March 2001, the sample preparation operations were moved to Building 

46. Analytical chemistry operations ended in late 2003. Some sample preparation for off-site analysis 

was conducted in a small area of Building 32 until at least 2007. Analytical Chemistry Operations in 

Building 20 were related, but less hazardous than sample grinding, crushing, mixing, etc. in a 

ventilated but unenclosed area. The chemical digestions of rock and soil samples in Building 20 were 

carried out in hoods which were necessary because of the strong acids used. 

Prior to January 1, 1986, air monitoring data from the Sample Preparation Laboratory are unavailable, 

other than the maximum measured uranium concentration in July 1980. During the first quarter of 

1986, when samples potentially containing ore and/or tailings were prepared for the NURE and 

GJRAP programs, intake rates were calculated based on the maximum permissible concentration 

(MPC) Exposures limit. A memo from B. Rothman to A. N. Tschaeche (Rothman, 1986) is an 

example of MPC time-weighted exposures for the first quarter of 1986 for [Redacted per Privacy Act]

workers performing grinding of uranium mill tailings. In the memo, the quarterly limit of 520 MPChours was provided. The existence of this memo is evidence that at least by 1986, worker intakes 

were being monitored and controlled using the MPC-hour limit. In the memo, Thorium-230 was used 

as the limiting radionuclide. 

Building 7A was constructed (as a Sample Preparation Laboratory) as an addition to Building 7 in 

1956. Reconstruction and remodeling of the facility took place during the period from 1978 through

1986 (WASTREN, 2001a). Due to these renovation activities, NIOSH has no assurance that the air 

concentrations measured in 1986 are representative for the period prior to the renovations. There were 

no renovations to the facility after 1986. NIOSH finds the single measurement from July 1980 to be 

insufficient to characterize intakes.

In a document entitled Technical Basis for Bioassay Sampling for Sample Preparation Plant and 

Grand Junction Vicinity Property Workers, dated March 1990, a set of air monitoring data are 

presented for the Sample Preparation Laboratory (UNC Geotech, 1990, PDF p.9). The data consist of 

isotopic air concentration measurements for Po-210, Ra-226, Th-230, Pb-210, U-238, and Bi-210. 

The data from these measurements are evaluated in the document whereby it is shown that Th-230 

contributes to over 90% of the overall Committed Effective Dose Equivalent (CEDE) of the 

radionuclide mixture. 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

29 of 47

It is unlikely that any worker would have routinely been exposed to airborne concentration exceeding 

the MPC limit without corrective actions being implemented. Although workers in the Sample Prep 

Lab were routinely issued respirators, NIOSH assumes that the respirators provided zero protection. 

For the period of time from January 1, 1986 through December 31, 1990, bounding daily uranium 

intake rates for operators and laborers may be assigned by assuming that a worker received the MPChour limit every quarter. Thorium-230 may be assumed to be the limiting radionuclide. The 

applicable limiting MPC for Thorium-230 is 2.00E-12 μCi/mL (Heffelfinger, 1981). Uranium intakes 

for supervisors and office workers for this time period may be assigned as a ratio of the 

operator/laborer intake rate using guidance from Battelle-TBD-6000. 

The document, Technical Basis for Bioassay Sampling for Sample Preparation Plant and Grand 

Junction Vicinity Property Workers (UNC Geotech, 1990), lays out the implementation of DOE Order 

5840.11 for monitoring workers. In the document, it specifies that bioassay shall be collected if 

exposure indicates that a worker could be exposed to inhalation intake during the year that exceeded 

200 DAC-hours. In addition, it indicates that a monitoring program must be in place for all workers 

that have the potential for 40 DAC-hours. Since this document was issued in early 1990, it is assumed 

that full implementation was not until the end of the year. Therefore, starting in 1991, it is assumed 

that unmonitored radiation workers would not have exceeded 200 DAC-hours in a given year (if they 

had they would have then been placed on a bioassay program). In addition, it is assumed that nonradiation workers would not have exceeded 40 DAC-hours in a given year. This document also 

reiterates that the controlling radionuclide was Thorium-230. The limiting DAC for Thorium-230 is 

3.00E-12 μCi/mL (Heffelfinger, 1981). The isotopic ratios of the different radionuclides found in 

various uranium source materials processed at the Grand Junction Facility Sampling Plant after 1985 

have been well characterized (Donivan, 1987). These ratios may be used to assign intakes of these 

other radionuclides, as a function of the Th-230 intake. 

For an office worker scenario, a wealth of data was located in close-out survey reports. These reports 

summarized the characterization data that had been collected prior to the remediation or 

decommissioning of the site buildings. A summary of the characterization data is provided in

NIOSH’s 2011 SEC-00175 Evaluation Report (NIOSH, 2011). A review of the data indicates that 

most of the removable contamination was in inaccessible areas and was normally less than 1000 

dpm/100 cm2

. This was also the Grand Junction limit for removable alpha or beta-gamma 

contamination. Therefore, 1000 dpm/100 cm2 could be used with an appropriate re-suspension factor 

and respiration rate to calculate a bounding intake for either an office worker exposed to residual 

contamination or an analytical laboratory worker whose work area would have been controlled to well 

below this level on a long-term basis.

Investigations for site remediation began in 1984. The remedial investigation/feasibility study (RI/FS) 

was done in 1989. The Record of Decision (ROD) was approved in 1990 (GJ MAP, 1996). The 

tailings were removed in 1989-1994. A close-out survey by the independent verification contractor 

(IVC) for the outdoor areas of the site was completed in 1995 (Forbes, 1997). Additional close-out 

surveys and verifications were done for each building on site that was released for unrestricted use

(Attachment 1 of NIOSH, 2011). Each close-out report includes a statement about the successful use 

of health and safety practices during the clean-up. In 2001, the site was turned over to a non-profit 

corporation and DOE leased back office and laboratory space.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

30 of 47

Thousands of pages of health and safety data (e.g., RWPs, survey maps, field measurements, air

samples) have been recently captured for the period 1991-2007, when most of the D&D activities took 

place (Building 7 H&S Data, 1991-2001; Building 11 H&S Data, 1993-1997; Building 12 H&S Data, 

1991-2000; Building 18 H&S Data, 1991-2001; Building 20 H&S Data, 1990-2000; Building 26 H&S 

Data, 1980-1998; Building 28 H&S Data, 1986-2000; Building 29 H&S Data, 1997; Building 31/31A 

H&S Data, 1990-1992; Building 36 H&S Data, 1992-1996; Health and Safety Checklists, 1990-

1991). Some bioassay data have also been captured for the period 1995-1999. There is no database of 

results that can readily be used for a co-worker study. However, from these data it is evident that the 

most highly-exposed workers were monitored. If no data are available for a D&D worker, the 

bounding dose scenario can be constructed from the health and safety data. For example, Buildings 7 

and 7A were used for sample preparation and were extensively contaminated. Building 7 was 

remediated to unrestricted area levels and was transferred to the U.S. Army Reserve. Contaminated 

concrete was removed with a concrete saw and jack-hammer or “scabbled” (mechanical removal of a 

thin layer by a power tool). Walls with internal contamination were removed and rebuilt. Health and 

Safety monitoring data are available for these operations (Building 7 H&S Data, 1991-2001; Building 

7A H&S Data, 1991-2001; Building 7A H&S Data, 2001; Building 7 H&S Data - Phase I, 1972-1999; 

Building 7 H&S Data - Phase II, 1980-2000). The bounding dose could then be assigned to other 

years with less data or less-intrusive work. NIOSH concludes that sufficient data are available to 

bound doses for D&D workers. By extension, these doses would bound workers with jobs requiring 

less exposure to contaminated materials. 

Bounding Inhalation Intakes from Ra-226, Th-230, and Th-232

During a site characterization in 1985, the Th-232 in soils was insignificant compared to Ra-226 and 

would contribute a negligible additional dose (Henwood, 1986, pdf pp. 47-54).

For 1975-2001, the primary source term for an office worker in a former sampling building was 

yellowcake. Sample preparation and analytical laboratory workers were mainly exposed to non-ore 

materials and occasionally ore samples during NURE work. The UMTRA program and other 

environmental restoration activities carried out by Grand Junction only required the analysis of 

relatively small, low-activity samples. However, the chemical work was carried out in fume hoods. 

Protection from the highly-toxic acids used to digest rock samples would also have protected the 

workers from radioactive materials (Environmental Monitoring, 1980). Similarly, the sample 

preparation area required adequate ventilation to protect workers from silica dust, which would also 

have provided protection from radioactive materials. D&D workers were exposed to yellowcake 

during D&D of the sampling buildings (e.g., Buildings 7 and 7A). They were also potentially 

exposed to tailings during D&D of the former Large Pilot Plant buildings (31, 33, 34, and 35). 

Workers (mainly subcontractors) were exposed to tailings during the remediation of tailings and open 

land areas in 1989-1994. There is ample evidence of protective measures (i.e., dust suppression), 

H&S monitoring, and bioassays being collected during these operations (Health and Safety 

Checklists, 1990-1991). Some bioassay samples were analyzed for Th-230 and Ra-226 (see Table 6-

1), indicating the site’s awareness of the hazards of uranium tailings. Other workers on site who were 

not directly involved in the D&D of the former Large Pilot Plant buildings or the remediation of open 

land areas may have been exposed to Ra-226 and Th-230 from tailings as a result of this work. The 

dose to these workers can be accounted for by assigning ambient environmental internal dose.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

31 of 47

There were only two campaigns involving thorium that took place after 1985. The first was the 

construction of the TL/TH pads (Steele, 1987). This operation, at least the thorium-handling part of 

the operation, was completed in 1986. The only other thorium campaign taking place at Grand 

Junction after 1985 was the manufacturing of the mixed uranium-thorium reference materials 

(Donivan, 1988), which was completed in 1988. 

NIOSH finds that the method for bounding uranium intakes during this time period is also appropriate 

to bound thorium intakes for the same period. The rationale for this conclusion is that because the 

controls used for crushing and grinding uranium ore were the same as those used for crushing and 

grinding thorium, and both operations took place in the same facility, Bldg. 7A. Although the activity 

concentrations of the thorium and uranium ores were not identical, the target concentrations for the 

resulting thorium and uranium calibration models that were being produced were very similar, in 

terms of radioactivity. Therefore, if the specific activity of the thorium ores were higher than that of 

the uranium ores, corresponding less thorium ore would have be required to produce the thoriumcontaining models. 

Based on interviews (Personal Communication, 2014e; Personal Communication, 2014g; Personal 

Communication, 2014h) with former workers, the time required to complete the construction of a 

calibration pad, either uranium or thorium, would not exceed a calendar month. The physical crushing 

and grinding of the thorium ore, which is the main source of exposure, would actually have been 

completed in much less time than a full month. For the purpose of bounding potential intakes of 

thorium from these operations a full calendar month of exposure to thorium ore is assumed for each 

operation involving crushing and grinding of thorium ore. Laborers and operators may therefore be 

assumed to be exposed to the MPC for a full month for each thorium operation if employed at that 

time. Since the exact dates of the construction of the pads are not known, the most claimant-favorable 

period (first potential month) should be assumed for the assignment of the thorium exposure. 

Thorium progeny should also be assumed to also be present, and at the same concentration as Th-232.

Bounding Intakes of Radon and Radon Decay Products (including thoron)

By February 1975, the last of the 103,776 drums of uranium concentrates had been shipped from the 

site. Because these drums contained between a few hundred pounds to a few tons of Ra-226, they 

probably represented a relatively minor source of radon exposures. Although concentrate sampling 

operations were reported to have ended in 1971, it is unclear whether this also applied to ore 

sampling, which was a potential source of radon exposures. In any case, by February 1975, the 

amount of material stored on site was greatly reduced and the site’s primary mission was the NURE 

program. 

The NURE program was not a uranium exploration program. Rather, extensive geologic studies were 

done to identify and evaluate geologic environments favorable for locating uranium (Albrethsen, 

1986). On-site sample preparation and analytical activities were primarily on non-ore materials. 

After the operational period ended on January 31, 1975, the Ra-226 in surface contamination, and in 

soils under/around the buildings, remained relatively constant until the remediation of the outdoor 

areas.

Radon in buildings was studied extensively in the D&D era (1989-2001). There are indoor 

radon-decay-product measurements for most of the buildings, including 300 daughter measurements 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

32 of 47

taken in 1985 in some of the former pilot plant buildings. Only Building 34, the former boiler 

building for the Large Pilot Plant, exceeded 0.02 WL (averaged over 100 hours) (Henwood, 1986, pdf 

p. 36). This building had been used to store ore and yellowcake and was not routinely occupied

(Facility Tour, 1984, pdf p. 2). In 1990, the site implemented and participated in the DOE radon study 

that included all occupied buildings on site at that time. The study’s measurements were 

representative of the highest radon levels in those portions of the buildings that were fit for occupancy 

(Radon, 1989-1990, pdf p. 19). An analysis of these data indicates that the median concentrations 

were less than 2 pCi/l or 0.010 WL. Only three buildings were greater than 4 pCi/l or 0.020 WL: 

Building 26 (4.5 pCi/l), Building 30B (5.7 pCi/l), and Building 32 (4.9 pCi/l). These buildings were 

reassessed in 1997-1998 after remediation and all measured less than 0.008 WL (1.6 pCi/l) 

(Attachment 1 of NIOSH, 2011). The available radon measurements can be used to establish a 

bounding dose from radon and radon decay products for February 1, 1975 to December 31, 2001. 

After 2001, the site radon values were reduced to background levels and there were no occupational 

exposures to radon at the Grand Junction site.

Routine calibration of thoron instruments took place at Grand Junction (George, 1992; Pearson, 

1990), indicating that the site was capable of measuring thoron levels; however, no specific thoron 

measurements have been identified. For the purpose of providing a claimant-favorable estimate of the 

thoron concentrations to which workers were potentially exposed, thoron levels are assumed to be 

equivalent to that of radon. This is considered bounding, as the thoron source term (thorium) would 

be much less than that of the radon source term (uranium/radium). Therefore it is unlikely that the 

thoron air concentration would exceed the radon air concentration. 

7.2.4 Internal Dose Reconstruction Feasibility Conclusion

NIOSH finds it is not feasible to estimate internal dose with sufficient accuracy for all workers on site 

from February 1, 1975 through December 31, 1985. There is insufficient information to estimate 

intakes of uranium and thorium (and associated progeny) until January 1, 1986. NIOSH has identified 

sufficient information and data to support bounding internal dose for the January 1, 1986 through July 

31, 2010 period using available methodologies.

Although NIOSH found that it is not possible to completely reconstruct internal radiation doses for the 

period from February 1, 1975 through December 31, 1985, NIOSH intends to use any internal 

monitoring data that may become available for an individual claim (and that can be interpreted using 

existing NIOSH dose reconstruction processes or procedures). Dose reconstructions for individuals 

employed at the Grand Junction Facilities site during the period from February 1, 1975 through 

December 31, 1985, but who do not qualify for inclusion in the SEC, may be performed using these 

data as appropriate.

7.5 Summary of Feasibility Findings for Petition SEC-00175, Addendum

This report evaluates the feasibility for completing dose reconstructions for employees at the Grand 

Junction Facilities from February 1, 1975 through July 31, 2010. NIOSH found that the available 

monitoring records, process descriptions and source term data available are insufficient to estimate the 

complete radiation dose for the period from February 1, 1975 through December 31, 1985. Doses for 

later years (January 1, 1986 through July 31, 2010) can be reconstructed.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

33 of 47

The feasibility findings presented in the initial SEC-00175 Evaluation Report (Table 7-3) for the 

period of March 23, 1943 through January 31, 1975, have not changed as a result of the present 

evaluation and are therefore not reproduced here. Table 7-3a below summarizes the results of the 

feasibility findings at the Grand Junction Facilities for each exposure source during the time period 

evaluated in this addendum, from February 1, 1975 through July 31, 2010.

Note: Table 7-3a is intended to supplement the information in Table 7-3 in the 2011 SEC-00175 

Evaluation Report. This table does not replace the existing Table 7-3 in the SEC-00175 Evaluation 

Report.

Table 7-3a: Summary of Addendum Feasibility Findings for SEC-00175

Source of Exposure

February 1, 1975 through

December 31, 1985

January 1, 1986 through

July 31, 2010

Reconstruction 

Feasible

Reconstruction 

Not Feasible

Reconstruction 

Feasible

Reconstruction 

Not Feasible

Internal X X

 - Radon and thoron X X

 - Thorium and Uranium and their

associated long-lived progeny

X X

External X X

 - Gamma X X

 - Beta X X

 - Neutron X X

 - Occupational Medical X-ray X X

Although NIOSH found that it is not possible to completely reconstruct radiation doses for the 

proposed class, NIOSH intends to use any internal and external monitoring data that may become 

available for an individual claim (and that can be interpreted using existing NIOSH dose 

reconstruction processes or procedures). Therefore, dose reconstructions for individuals employed at 

Grand Junction Facilities during the period from February 1, 1975 through December 31, 1985, but 

who do not qualify for inclusion in the SEC, may be performed using these data as appropriate.

8.0 Evaluation of Health Endangerment for Petition SEC-00175

The health endangerment determination for the class of employees covered by this evaluation report is 

governed by both EEOICPA and 42 C.F.R. § 83.13(c)(3). Under these requirements, if it is not 

feasible to estimate with sufficient accuracy radiation doses for members of the class, NIOSH must 

also determine that there is a reasonable likelihood that such radiation doses may have endangered the 

health of members of the class. Section 83.13 requires NIOSH to assume that any duration of 

unprotected exposure may have endangered the health of members of a class when it has been 

established that the class may have been exposed to radiation during a discrete incident likely to have 

involved levels of exposure similarly high to those occurring during nuclear criticality incidents. If 

the occurrence of such an exceptionally high-level exposure has not been established, then NIOSH is 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

34 of 47

required to specify that health was endangered for those workers who were employed for a number of 

work days aggregating at least 250 work days within the parameters established for the class or in 

combination with work days within the parameters established for one or more other classes of 

employees in the SEC. 

NIOSH’s evaluation determined that it is not feasible to estimate the complete radiation dose for all 

workers from February 1, 1975 through December 31, 1985. Modification of the class definition 

regarding health endangerment and minimum required employment periods, therefore, is required. 

For the later years in the evaluated class (January 1, 1986 through July 31, 2010), a health 

endangerment determination is not required because NIOSH has determined that it has an established 

methodology for estimating dose.

9.0 Class Conclusion for Petition SEC-00175

Based on its full research of the class under evaluation, NIOSH has defined a single class of 

employees for which NIOSH cannot estimate radiation doses with sufficient accuracy. The NIOSHproposed class to be added to the SEC includes all employees of the Department of Energy, its 

predecessor agencies, and its contractors and subcontractors who worked at the Grand Junction 

Facilities site in Grand Junction, Colorado, during the period from February 1, 1975 through 

December 31, 1985, for a number of work days aggregating at least 250 work days, occurring either 

solely under this employment or in combination with work days within the parameters established for 

one or more other classes of employees in the SEC. 

There are sufficient data to reconstruct internal dose for the period from January 1, 1986 through July 

31, 2010. There are sufficient data to reconstruct external dose, including occupational medical dose,

for the period from February 1, 1975 through July 31, 2010. 

NIOSH has reviewed available technical resources and many other references, including the Site 

Research Database (SRDB), for information relevant to SEC-00175. In addition, NIOSH reviewed its 

NOCTS dose reconstruction database to identify EEOICPA-related dose reconstructions that might 

provide information relevant to the petition evaluation.

These actions are based on existing, approved NIOSH processes used in dose reconstruction for 

claims under EEOICPA. NIOSH’s guiding principle in conducting these dose reconstructions is to 

ensure that the assumptions used are fair, consistent, and well-grounded in the best available science. 

Simultaneously, uncertainties in the science and data must be handled to the advantage, rather than to 

the detriment, of the petitioners. When adequate personal dose monitoring information is not 

available, or is very limited, NIOSH may use the highest reasonably possible radiation dose, based on 

reliable science, documented experience, and relevant data to determine the feasibility of 

reconstructing the dose of an SEC petition class. NIOSH contends that it has complied with these 

standards of performance in determining the feasibility or infeasibility of reconstructing dose for the 

class under evaluation.
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

35 of 47

10.0 References for this Addendum

42 C.F.R. pt. 83, Procedures for Designating Classes of Employees as Members of the Special 

Exposure Cohort Under the Energy Employees Occupational Illness Compensation Program Act of 

2000; Final Rule; May 28, 2004; SRDB Ref ID: 22001

42 U.S.C. §§ 7384-7385 [EEOICPA], Energy Employees Occupational Illness Compensation 

Program Act of 2000, as amended

Air Sampling, Nov-Dec1990, Airborne Radioparticulate Sampling Data Sheets for NovemberDecember 1990; completed by various health physics technicians; various dates throughout 

November-December 1990; SRDB Ref ID: 89909

Airborne Radioparticulates, 1994, Airborne Radioparticulate Sampling Data Sheets, Grand Junction 

Projects Office (GJPO); various dates in 1994; SRDB Ref ID: 89872, PDF pp. 275-341

Albrethsen, 1986, A Summary History of the Activities of the Grand Junction Office of the AEC, 

ERDA, and DOE; Al Albrethsen, Bill Chenoweth, and Frank McGinley; September 1986; SRDB Ref 

ID: 3325, PDF pp. 14-26

Bioassay, Jan1984-Dec1986, Urinalysis Sample Logs for January 1984-December 1986; Bendix Field 

Engineering Corporation; various dates between January 1984-December 1986; SRDB Ref ID: 98107

Bioassay, Apr1985-Mar1987, Bioassay Records for April 1985-March 1987; various vendors; various 

dates between April 1985-March 1987; SRDB Ref ID: 98096

Building 7 H&S Data, 1991-2001, Compilation of Building 7 Health and Safety Information and 

Data; various contractors at the Grand Junction Projects Office; various dates in 1991-2001; SRDB 

Ref ID: 89872

Building 7 H&S Data - Phase I, 1972-1999, Compilation of Building 7 Phase I Health and Safety 

Information and Data, various contractors at the Grand Junction Projects Office; various dates in 

1972-1999; SRDB Ref ID: 90164

Building 7 H&S Data - Phase II, 1980-2000, Compilation of Building 7 Phase II Health and Safety 

Information and Data, various contractors at the Grand Junction Projects Office; various dates in 

1980-2000; SRDB Ref ID: 90155

Building 7A H&S Data, 1991-2001, Compilation of Building 7A Health and Safety Information and 

Data, various contractors at the Grand Junction Projects Office; various dates in 1991-2001; SRDB 

Ref ID: 90118

Building 7A H&S Data, 2001, Compilation of Building 7A Health and Safety Information and Data, 

various contractors at the Grand Junction Projects Office; various dates in 2001; SRDB Ref ID: 90154

Building 11 H&S Data, 1993-1997, Compilation of Building 11 Health and Safety Information and 

Data, various contractors at the Grand Junction Office (GJO); various dates in 1993-1997; SRDB Ref 

ID: 89928
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

36 of 47

Building 12 H&S Data, 1991-2000, Compilation of Building 12 Health and Safety Information and 

Data, various contractors at the Grand Junction Office (GJO); various dates in 1991-2000; SRDB Ref 

ID: 89926

Building 18 H&S Data, 1991-2001, Compilation of Building 18 Health and Safety Information and 

Data, various contractors at the Grand Junction Office (GJO); various dates in 1991-2001; SRDB Ref 

ID: 89931

Building 20 H&S Data, 1990-2000, Compilation of Building 20 Health and Safety Information and 

Data, various contractors at the Grand Junction Office (GJO); various dates in 1990-2000; SRDB Ref 

ID: 89938

Building 26 H&S Data, 1980-1998, Compilation of Building 26 Health and Safety Information and 

Data, various contractors at the Grand Junction Office (GJO); various dates in 1980-1998; SRDB Ref 

ID: 89942

Building 28 H&S Data, 1986-2000, Compilation of Building 28 Health and Safety Information and 

Data, various contractors at the Grand Junction Office (GJO); various dates in 1986-2000; SRDB Ref 

ID: 89979

Building 29 H&S Data, 1997, Compilation of Building 29 Health and Safety Information and Data, 

various contractors at the Grand Junction Office (GJO); various dates in 1997; SRDB Ref ID: 89966

Building 31/31A H&S Data, 1990-1992, Compilation of Building 31/31A Health and Safety 

Information and Data, various contractors at the Grand Junction Office (GJO); various dates in 1990-

1992; SRDB Ref ID: 89991

Building 36 H&S Data, 1992-1996, Compilation of Building 36 Health and Safety Information and 

Data, various contractors at the Grand Junction Office (GJO); various dates in 1992-1996; SRDB Ref 

ID: 90015

Building 938 H&S Data, 1993-1999, Compilation of Building 938 Health and Safety Information and 

Data; various contractors at the Grand Junction Office (GJO); various dates in 1993-1999; SRDB Ref 

ID: 90087

Building 3022 H&S Data, 1980-2000, Compilation of Building 3022 Health and Safety Information 

and Data; various contractors at the Grand Junction Office (GJO); various dates in 1980-2000; SRDB 

Ref ID: 90105

D&D Reports, 1985-1999, Compilation of Buildings 33 and 35 Decontamination and 

Decommissioning Documentation; various contractors at the Grand Junction Projects Office; various 

dates in 1985-1999; SRDB Ref ID: 93709

D&D Report, 1995, Final Report of the Decontamination and Decommissioning of the Exterior Land 

Areas at the Grand Junction Projects Office Facility, U.S. Department of Energy, Grand Junction 

Projects Office Remedial Action Project; September 1995; SRDB Ref ID: 88610 
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

37 of 47

Donivan, 1987, Uranium Reference Materials, DOE/ID/12584-9; Stephen Donivan and Ronald 

Chessmore; July 1987; SRDB Ref ID: 140369

Donivan, 1988, Soil-Based Uranium Disequilibrium and Mixed Uranium-Thorium Series 

Radionuclide Reference Materials, UNC/GJ-37(TMC); Stephen Donivan and Ronald Chessmore; 

December 1988; SRDB Ref ID: 93756

Dosimetry, 1986-2007, Grand Junction Spreadsheet from INEL Dosimetry Database; dates from 

January 1986-December 2007; SRDB Ref ID: 107374

Environmental Monitoring, 1980, 1980 Environmental Monitoring Report for the U.S. Department of 

Energy Facilities Grand Junction, Colorado, and Monticello, Utah; prepared by Nic Korte and Ralph 

Thul, Bendix Field Engineering Corporation; April 1981; SRDB Ref ID: 90862

Environmental Monitoring, 1986, Environmental Monitoring Report on Department of Energy 

Facilities at Grand Junction, Colorado, and Monticello, Utah, for Calendar Year 1986; prepared by 

Michael Sewell and Larick Spencer, UNC; March 1987; SRDB Ref ID: 90851

Environmental Monitoring, 1987, Environmental Monitoring Report on the U.S. Department of 

Energy’s Grand Junction Projects Office Facility, Grand Junction, Colorado, for Calendar Year 

1987; U.S. Department of Energy Grand Junction Projects Office; May 1988; SRDB Ref ID: 90847

Environmental Monitoring, 1988, Environmental Monitoring Report on the U.S. Department of 

Energy’s Grand Junction Projects Office Facility, Grand Junction, Colorado, for Calendar Year 

1988; prepared by UNC Geotech; May 1989; SRDB Ref ID: 90846

Environmental Monitoring, 1989, Environmental Monitoring Report on the U.S. Department of 

Energy’s Grand Junction Projects Office Facility, Grand Junction, Colorado, for Calendar Year 

1989; prepared by UNC Geotech; May 1990; SRDB Ref ID: 90856

Environmental Monitoring, 1990, Grand Junction Projects Office Site Environmental Report for 

Calendar Year 1990; prepared by Chem-Nuclear Geotech, Inc.; May 1991; SRDB Ref ID: 90845

Environmental Monitoring, 1991, Grand Junction Projects Office Site Environmental Report for 

Calendar Year 1991; prepared by Chem-Nuclear Geotech, Inc.; May 1992; SRDB Ref ID: 90853

Environmental Monitoring, 1992, Grand Junction Projects Office Site Environmental Report for 

Calendar Year 1992; prepared by RUST Geotech Inc.; May 1993; SRDB Ref ID: 90860

Environmental Monitoring, 1993, Grand Junction Projects Office Site Environmental Report for 

Calendar Year 1993; prepared by RUST Geotech Inc.; May 1994; SRDB Ref ID: 90857

Facility Tour, 1984, GJAO – SFMP Facility Tour – June 29, 1984, Grand Junction Area Office; June 

29, 1984; SRDB Ref ID: 71090

Forbes, 1997, Confirmatory Radiological Survey of the Grand Junction Projects Office Remedial 

Action Project Exterior Portions, 1989-1995; G. H. Forbes and P. V. Egidi of Oak Ridge National 

Laboratory; April 1997; SRDB Ref ID: 76720
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

38 of 47

George, 1992, Evaluation of Thoron-Daughter Instruments, DOE/ID/12584-110; J. L. George; 

September 1992; SRDB Ref ID: 93715

GJ Contractors, undated, Other Contractors at the U.S. Department of Energy Grand Junction Office, 

Grand Junction, Colorado: Uranium Concentrate Sampling; Grand Junction Operations Office; 

undated; SRDB Ref ID: 3325, pdf p. 4

GJ MAP, 1996, Grand Junction Projects Office Management Action Process (MAP), prepared for the 

U.S. Department of Energy by Rust Geotech; April 1996; SRDB 88611, pdf p. 21

Health and Safety Checklists, 1990-1991, Collection of Health and Safety Checklists, UNC Geotech

and Grand Junction Projects Office; various dates in 1990-1991; SRDB Ref ID: 89900

Heffelfinger, 1981, Environmental Protection, Safety, and Health Protection Program for DOE 

Operations, DOE 5480.1 Chg 6; William S. Heffelfinger; August 13, 1981; SRDB Ref ID: 11593

Henwood, 1986, Radiologic Characterization of the Department of Energy Grand Junction Projects 

Office Facility; Paul Henwood and Callie Ridolfi; January 1986; SRDB Ref ID: 6640

Leino, 1994, Field Calibration Facilities for Environmental Measurement of Radium, Thorium, and 

Potassium, DOE/ID/12584-179; R. Leino, D. C. George, B. N. Key, L. Knight, and W. D. Steele; 

June 1994; SRDB Ref ID: 93424

Mathews, 1978, DOE-Grand Junction Logging Model Data Synopsis, GJBX-76(78); Mark A. 

Mathews, Carl J. Kolzumi, and Hilton B. Evans; May 1978; SRDB Ref ID: 97466

NIOSH, 2011, SEC Petition Evaluation Report for Petition SEC-00175, Grand Junction Operations 

Office; National Institute for Occupational Safety and Health (NIOSH); January 11, 2011; SRDB Ref 

ID: 141458

OCAS-PR-004, Internal Procedures for the Evaluation of Special Exposure Cohort Petitions, Rev. 0; 

National Institute for Occupational Safety and Health (NIOSH); Cincinnati, Ohio; September 23, 

2004; SRDB Ref ID: 32022

Pearson, 1990, Calibration of Alpha-Track Monitors for Measurement of Thoron, DOE/ID/12584-61; 

Mark D. Pearson; March 1990; SRDB Ref ID: 93747

Personal Communication, 2010b, Personal Communication with a Former Grand Junction Employee; 

Telephone Interview by ORAU Team; October 19, 2010; SRDB Ref ID: 90653

Personal Communication, 2010c, Personal Communication with a Former Grand Junction Employee; 

Telephone Interview by ORAU Team; October 14, 2010; SRDB Ref ID: 90654

Personal Communication, 2010d, Personal Communication with a Former Grand Junction Employee; 

Telephone Interview by ORAU Team; October 19, 2010; SRDB Ref ID: 90655

Personal Communication, 2010h, Personal Communication with a Former Grand Junction Employee; 

Telephone Interview by ORAU Team; December 2, 2010; SRDB Ref ID: 90999
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

39 of 47

Personal Communication, 2014e, Personal Communication with a Former Grand Junction Employee; 

Telephone Interview by ORAU Team; December 18, 2014, 11:00 AM EST; SRDB Ref ID: 139114

Personal Communication, 2014g, Personal Communication with a Former Grand Junction Employee; 

Telephone Interview by ORAU Team; December 10, 2014, 11:00 AM EST; SRDB Ref ID: 139116

Personal Communication, 2014h, Personal Communication with a Former Grand Junction Employee; 

Telephone Interview by ORAU Team; October 24, 2014, 9:00 AM MST; SRDB Ref ID: 139128

Procedure, 1990, Internal Radiation Dosimetry Program, ES&H Procedure 3.8, UNC Geotech, 

October 3, 1990; SRDB Ref ID: 90529

Radon, 1989-1990, Results of the U.S. Department of Energy Indoor Radon Study, Volume 1; 

prepared by UNC Geotech; results compiled August 1990; SRDB Ref ID: 13191

Rothman, 1986, Summary of MPC-Time Weighted Exposure for the First Quarter, correspondence to 

A. N. Tschaeche; B. Rothman; April 1, 1986; SRDB Ref ID: 98100

Ruhoff, 1943, Frequency of Physical and Laboratory Examinations, correspondence to Area 

Engineer, Colorado Area; J. Ruhoff; November 9, 1943; SRDB Ref ID: 4504

Steele, 1987, Construction and Characterization of the TL/TH Thorium Calibration Pads, 

DOE/ID/12584-3; W. Douglass Steele; September 1987; SRDB Ref ID: 93754

UNC Geotech, 1990, Technical Basis for Bioassay Sampling for Sample Preparation Plant and 

Grand Junction Vicinity Property Workers; UNC Geotech; March 1990; SRDB Ref ID: 100231

Vanderheiden, 1993, Grand Junction Projects Office Site Decontamination and/or Decommissioning 

Project Plan, with cover letter; Tom Vanderheiden; February 23, 1993; SRDB Ref ID: 93686

Ward, 1978, Procedures and Regulations for Airport Calibration Pads Walker Field, Grand Junction, 

Colorado, GJBX-38(78); Dan L. Ward and David C. Stromswold; August 1978; SRDB Ref ID: 93152

WASTREN, 2001a, Closeout Report of the Decontamination and Decommissioning of the Sample 

Plant (Phase III) of Building 7 at the Grand Junction Office Facility, GJO-2001-252-FOS; 

WASTREN, Inc.; September 2001; SRDB Ref ID: 89880

WASTREN, 2001b, Decontamination and Decommissioning of the Grand Junction Office Facility—

Certification Docket Summary Report (activities through fiscal year 2001), GJO-2001-254-FOS; 

WASTREN, Inc.; September 2001; SRDB Ref ID: 90206
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

40 of 47

This page intentionally left blank
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

41 of 47

Attachment 2: Data Capture Synopsis

Table A2-1: Summary of Holdings in the SRDB for Grand Junction Facilities

Data Capture Information Data Capture Description Completed Uploaded 

into SRDB

Primary Site/Company Name: Grand Junction 

Facilities (GJF), formerly Grand Junction 

Operations Office; (GJO), (GJOO) 1943 -

Present DOE 

 

Alternate Site Names: 

U.S. Vanadium (Stratcor), 1943-1946, Robert 

Elliot American Smelting and Refining Co. 

(ASARCO) 1948-1955, Tom Aldridge 

Ledoux and Company 1948, Charley Avalon 

American Cyanamid (Wyeth) 1953-1954, 

Denise Lenza National Lead Co. (NL 

Industries) 1954-1958, Paul Bass Lucius 

Pitkin, Inc. 1956-1971, James McLaughlin 

Bendix Field Engineering Corporation 1975-

1986 UNC Technical Services 

1986-1987 UNC 

Geotech, Inc. 1987-1990 

Chem-Nuclear Geotech, Inc. 1990-1993 

RUST Geotech, Inc. 1993-1996 

MACTEC Environmental Restoration Services 

1996-2002 WASTREN, Inc. 1996-2002 

S.M. Stoller Corporation 2002-Present

Physical Size and Population of the Site:

The site encompasses 54 acres. In 1964 there 

were 226 workers on site, 24 of whom were 

monitored for radiation exposure. In 1998 307 

workers were monitored for radiation exposure.

Material received from GJO or downloaded from the GJO website is 

summarized in the DOE Legacy Management - Grand Junction Office and 

Internet - DOE Legacy Management Considered Sites sections below. 

NL Industries has informed the Project that a formal court order or records 

subpoena will be required before any GJO records that may exist can be 

released or disclosed. The other company’s records were either destroyed 

or submitted to GJO. 

11/30/2009 0

State Contacted: Steve Tarlton, Phil Egidi Colorado does not hold relevant records. 11/11/2009 0

Battelle Memorial Institute, King Avenue Normal and product material inventories. 04/14/2011 1

Brookhaven National Laboratory A Department of Energy report from 2000 that states that GJO does not 

conduct ambient particulate or tritium air monitoring.

03/01/2006 1

Colorado Mesa University, Tomlinson Library Monthly progress reports, topical uranium extraction reports, the history of 10/15/2012 51
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

42 of 47

Table A2-1: Summary of Holdings in the SRDB for Grand Junction Facilities

Data Capture Information Data Capture Description Completed Uploaded 

into SRDB

the Colorado plateau uranium industry, pilot plant progress reports, and a 

pilot ion exchange equipment report.

Department of Labor / Paragon A summary history of uranium mills, the Surgeon General's 

recommendations regarding building homes on uranium mill tailings, and 

an Atomic Energy Commission report on contamination removal.

01/23/2012 11

DOE Environmental Measurements Laboratory 

Library

Mill tailings project reports, dust sample reports, and a report on controlling 

employee exposures in underground uranium mines.

03/09/2005 5

DOE Germantown The DOE Legacy Management process for responding to EEOICPA 

claims.

03/07/2011 1

DOE Legacy Management - Grand Junction 

Office

A listing of all contractors at GJO, summary histories of GJO, a summary 

history of domestic uranium procurement, Contract No. AT(05-1)-266 

documents, material inventories, reports on the treatment of carnotite ores, 

annual UMTRA site inspections, UMTRA reports, remediation work plans, 

the S.M. Stoller Office of Legacy Management contract, reports on the 

treatment of ore concentrates, reports on standards preparation, 1953 trip 

reports, a mixed waste report, final decontamination and decommissioning 

reports, the Manhattan Engineer District diagram of materials shipments, 

environmental reports, airborne effluent control at uranium mills, a 1980 

radiometric site survey, a 1997 confirmation of exterior remediation 

activities, radon reports, a summary of process knowledge interviews, mill 

tailings studies and reports, the 1959 mill products sampling process and 

flow sheet, building decontamination and decommissioning reports with 

supporting and historical radiological survey data, and bioassay data from 

1967 and the 1990s.

01/29/2015 469

DOE Legacy Management - Morgantown A 1972 unclassified Fernald letter log with GJO correspondence, a Fernald 

report which mentions Colorado ores, and verification of GJO as the 

location of an ore concentrate stockpile. 

09/19/2011 408

DOE Legacy Management - MoundView 

(Fernald Holdings, includes Fernald Legal 

Database)

A 1953 Health and Safety Division report which references instruments in 

use at GJO, raw materials development report for 1954-1959, a report 

which documents the analysis of GJO U3O8 at the New Brunswick 

Laboratory, data on ore concentrate shipments from GJO to Fernald in the 

1970s, limited uranium urinalysis from the 1950s and 1960, ore concentrate 

treatment methods at Fernald, Mallinckrodt Chemical Co., and Weldon 

Spring, interlaboratory comparisons of ore concentrate assays, an ore 

concentrate management plan, ore sampling flow diagrams under Lucius 

Pitkin, ore concentrate specifications committee meeting minutes, an 

epidemiologic study of mill worker mortality, ore concentrate inventories 

05/13/2010 51
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

43 of 47

Table A2-1: Summary of Holdings in the SRDB for Grand Junction Facilities

Data Capture Information Data Capture Description Completed Uploaded 

into SRDB

and projections, a 1953 New York Operations Office report with the 

summary of distribution of film badge readings, and documentation of a 

security breach during a concentrate shipment.

DOE National Nuclear Security Administration 

(NNSA)

National Environmental Policy Act (NEPA) categorical exemptions for 

GJO projects and National Uranium Resource Evaluation (NURE) 

contracted activities.

01/17/2012 6

DOE Oak Ridge Operations Office Records 

Holding Task Group (ORO-RHTG)

Uranium production reports. 06/25/2013 21

DOE Office of Scientific and Technical 

Information (OSTI)

Environmental restoration site maps and sampling and testing procedures 

for special products.

09/16/2010 2

Federal Records Center, Kansas City Film badge records for 1957-1960, Uranium Mill Tailings Remedial Action 

Project (UMTRAP) Project Health and Safety Plan, and an Argonne report 

describing radon flux tests at Grand Junction.

10/15/2008 6

Federal Records Center, San Bruno A 1988 Lawrence Berkeley National Laboratory environmental sampling 

and analysis plan which identifies GJO as the low level radioanalytical 

laboratory to be used.

08/03/2012 1

Hanford 1948 uranium inventories and the authority to declassify raw materials 

program documents.

03/20/2013 2

Idaho National Laboratory Dosimetry reports, bioassay reports, exposure summaries, area monitoring 

reports, and neutron survey data.

06/06/2012 29

Interlibrary Loan A 1958 uranium ore processing report and the proceedings of the 1993 

incineration conference.

05/29/2012 2

Internet - Defense Technical Information 

Center (DTIC)

A 1996 report on the decontamination, survey, and statistical release 

method for vehicles.

08/26/2014 1

Internet - DOE Environmental Management Linking Legacies Chapter 3: Wastes. 10/28/2007 1

Internet - DOE Comprehensive Epidemiologic 

Data Resource (CEDR)

No relevant data identified. 11/02/2009 0

Internet - DOE Hanford Declassified Document 

Retrieval System (DDRS)

No relevant data identified. 11/02/2009 0

Internet - DOE Legacy Management 

Considered Sites

A raw materials research report covering 1954-1959; mill tailings sites 

inspections, assessments, and remedial action plans, and long-term 

stewardship issues and updates. 

08/01/2012 14

Internet - DOE National Nuclear Security 

Administration (NNSA) - Nevada Site Office

No relevant data identified. 11/02/2009 0

Internet - DOE OpenNet A 1971 site visit report, a 1949 progress report, and Linking Legacies 

Appendix B: The Eight Major Processes of the Nuclear Weapons Complex.

11/02/2009 3
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

44 of 47

Table A2-1: Summary of Holdings in the SRDB for Grand Junction Facilities

Data Capture Information Data Capture Description Completed Uploaded 

into SRDB

Internet - DOE OpenNet / NIOSH The 1960 annual report to Congress. 01/11/2008 1

Internet - DOE OSTI Energy Citations Nuclear waste management reports, the overview of decommissioning 

activities, leaching of uranium from ores, and environmental audits and 

reports.

11/30/2013 14

Internet - DOE OSTI Information Bridge Stannard's Radioactivity and Health, final decontamination and 

decommissioning reports, the long term surveillance plan for the Cheney 

Disposal Site, complex-wide radiological waste data, final report on the 

decontamination and decommissioning of exterior land areas, waste 

generation and pollution prevention reports, final decontamination and 

decommissioning reports for GJO facilities, Uranium Mill Tailings 

Remedial Action (UMTRA) reports, groundwater protection reports, ore 

processing reports, a radon barrier system report, and uranium industry 

annuals.

07/30/2013 104

Internet - DOE OSTI SciTech Connect A survey of sources of thorium-230, the summary of GJO well logging 

model data, and the construction of the potassium-uranium-thorium (KUT) 

test pits.

06/10/2011 3

Internet - Energy Employees Claimant 

Assistance Project (EECAP)

Groundwater and surface water sampling, the radiological release reports 

for GJO buildings, the long-term surveillance and maintenance plan, and a 

GJO fact sheet.

12/13/2013 13

Internet - Google Environmental reports, groundwater reports, final decontamination and 

decommissioning reports, S.M. Stoller's contract for management of GJO, 

Projects Office Management Action Process, site environmental summary, 

the quantity of legacy material present at the site, overviews of mill tailings 

remediation, complex-wide waste management, stewardship, GJO REMS 

data, mixed waste profiles, ALARA analysis of hazardous waste disposal 

alternatives, mill tailings management plans, radon barrier analyses, annual 

NURE reports, and environmental restoration plans.

01/13/2015 117

Internet - Health Physics Journal No relevant data identified. 11/04/2010 0

Internet - Journal of Occupational and 

Environmental Health 

No relevant data identified. 11/04/2010 0

Internet - National Academies Press (NAP) No relevant data identified. 11/04/2009 0

Internet - NIOSH The designation of a class of GJO employees in the Special Exposure 

Cohort and the United Nuclear Corporation SEC Petition Evaluation 

Report. 

09/14/2011 2

Internet - NRC Agencywide Document Access 

and Management (ADAMS)

UMTRA surveillance and maintenance, inspection, mapping, engineering 

drawings, corrective action, and site remediation reports, Grand Junction 

Steel property cleanup, Freedom of Information Act (FOIA) requests and 

03/26/2013 191
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

45 of 47

Table A2-1: Summary of Holdings in the SRDB for Grand Junction Facilities

Data Capture Information Data Capture Description Completed Uploaded 

into SRDB

summaries, and radon barrier reports.

Internet - Oak Ridge National Laboratory 

(ORNL)

Design of an extraction plant, a 1956 feed material processing status report, 

a 1974 Health Physics Division report, a 1957 uranium recovery report, and 

the ORNL fiftieth anniversary history.

01/07/2013 5

Internet - U.S. Environmental Protection 

Agency (EPA)

A 1979 preliminary assessment of radon emanations from mill tailings 

piles.

09/09/2005 1

Internet - Washington State University (U.S. 

Transuranium and Uranium Registries)

No relevant data identified. 11/02/2009 0

Kansas City Plant (KCP) A KCP environmental restoration paper co-authored by GJO personnel. 09/19/2013 1

Mesa County Libraries, Grand Junction, CO Newspaper reports on GJO site management, property transfers, and 

workforce changes.

01/06/2011 26

Mound Museum Bismuth project reports. 02/13/2008 3

National Archives and Records Administration 

(NARA) -Atlanta

Manhattan Engineer District production, accountability, medical reports, 

and analysis of the first four lots produced at GJO.

06/19/2008 20

National Archives and Records Administration 

(NARA) -College Park

A 1974 study of inactive mill tailings piles, Madison Square Area material 

balance reports, a 1947 monthly status report, and special materials 

accountability reports.

09/11/2013 5

National Institute for Occupational Safety and 

Health (NIOSH)

Semiannual reports of the Atomic Energy Commission, a 1978 DOE survey 

memo and a 1971 New York Times article on houses built on mill tailings, 

1956 AEC radiation safety activities, and Volumes I and II of the History 

of the AEC.

08/27/2014 11

Nevada Test Site (NTS) The NTS Final Environmental Impact Statement which identifies GJO as a 

shipper of radioactive waste to NTS.

10/01/2003 1

New York State Archives A waste disposal report documenting the presence of GJO ore at Lake 

Ontario Ordnance Works (LOOW).

03/19/2012 1

Nuclear Regulatory Commission (NRC) Public 

Document Room

Uranium mills environmental monitoring reports, and source material 

licenses and licensing documentation.

10/26/2012 18

Oak Ridge Associated Universities (ORAU) 1985 through 2009 annual exposure totals spreadsheet. 11/02/2010 1

ORAU Team The tenth and eleventh annual radiation exposure reports and 21 

documented process knowledge interviews.

12/18/2014 23

Pacific Northwest National Laboratory A Nuclear Regulatory Commission guidance document for performing 

occupational radiation monitoring at uranium mills.

04/02/2006 1

SAIC Summary radiation exposure reports for 1960, 1961, 1964, 1969, 1972, and 

1973.

09/02/2004 6

Sandia National Laboratories, New Mexico 

(SNL/NM)

Weekly exposure reports for 1977-1979 and radioactive shipments from 

SNL/NM.

10/20/2010 2

S. Cohen & Associates (SC&A) Film badge reports and the classification review and release of 04/07/2011 3
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

46 of 47

Table A2-1: Summary of Holdings in the SRDB for Grand Junction Facilities

Data Capture Information Data Capture Description Completed Uploaded 

into SRDB

Mallinckrodt and United Nuclear documents held by GJO.

SC&A / Idaho National Laboratory A 1986 memo which states that the GJOO has nine CERCLA units. 06/24/2010 1

SC&A / Pinellas Plant A 1993 annual report on waste generation and waste minimization

progress.

06/24/2010 1

Southern Illinois University AEC construction cost differentials and the Argonne Palos Forest Preserve 

environmental monitoring program administered by DOE Legacy 

Management at GJO.

10/21/2008 2

Unknown Urine sample data, air sampling data, results of 1991 indoor radon study, 

film badge reports, site characterization surveys, New York Operations 

Office correspondence and reports, radon measurements, and a request for 

special J slugs.

10/04/2004 57

Total 1,720

Table A2-2: Database Searches for Grand Junction Facilities

Database/Source Keywords Hits Uploaded 

into SRDB

NOTE: Database search terms employed for each of the databases listed below are available

in the Excel file called “Copy of Grand Junction Facilities Rev 02 (83.13) 02-09-15.”

Defense Technical Information Center (DTIC)

https://www.dtic.mil/

COMPLETED 08/26/2014

See Note above 2,621 1

DOE CEDR

http://cedr.lbl.gov/

COMPLETED 11/02/2009

See Note above 0 0

DOE Hanford DDRS

http://www2.hanford.gov/declass/

COMPLETED 11/02/2009

See Note above 0 0

DOE NNSA - Nevada Site Office

www.nv.doe.gov/main/search.htm

COMPLETED 11/02/2009

See Note above 0 0

DOE OpenNet See Note above 36 8
SEC-00175 Addendum 03-12-2015 Grand Junction Facilities

47 of 47

Table A2-2: Database Searches for Grand Junction Facilities

Database/Source Keywords Hits Uploaded 

into SRDB

http://www.osti.gov/opennet/advancedsearch.jsp

COMPLETED 11/02/2009

DOE OSTI Energy Citations

http://www.osti.gov/energycitations/

COMPLETED 10/31/2009

See Note above 909 1

DOE OSTI Information Bridge

http://www.osti.gov/bridge/advancedsearch.jsp

COMPLETED 10/30/2009

See Note above 422 72

Energy Employees Claimant Assistance Project (EECAP)

http://www.eecap.org

COMPLETED 12/13/2013

See Note above NA 15

Google

http://www.google.com

COMPLETED 11/10/2009

See Note above 924,702 25

HP Journal

http://journals.lww.com/health-physics/pages/default.aspx

COMPLETED 11/04/2010

See Note above 53 0

Journal of Occupational and Environmental Health 

http://www.ijoeh.com/index.php/ijoeh

COMPLETED 11/04/2010

See Note above 1 0

National Academies Press

http://www.nap.edu/

COMPLETED 11/04/2009

See Note above 211 0

NRC ADAMS Reading Room

http://www.nrc.gov/reading-rm/adams/web-based.html

COMPLETED 09/01/2010

See Note above 1,211 51

U.S. Transuranium & Uranium Registries 

http://www.ustur.wsu.edu/

COMPLETED 11/02/2009

See Note above 0 0